Medical Treatment for Radiation Exposure
External Exposure Treatment
Inhalation Treatment
Internal Exposure
Ingestion Treatment
Injection Treatment
Absorption Treatment
Acute Radiation Effects
Radioactive Sources
Medical Sources
Consumer Products
Industrial Radiation Sources
Beta Emitter Dose Rates
Positron Emitters
Gamma Exposure Rates
Neutron Exposure Rates
Characteristic Radiations
Thorium-232 & Uranium-238 Decay Chains
SI and US “Traditional” Units
Abbreviations
Conversions
Constants
Units and Terminology
Emergency Response
Risk
Radon
2
2
4
7
7
7
7
11
13
13
24
29
32
33
34
45
48
50
63
64
65
70
71
72
78
79
Medical Treatment for Radiation Exposure
External Exposure Treatment
Inhalation Treatment
Internal Exposure
Ingestion Treatment
Injection Treatment
Absorption Treatment
Acute Radiation Effects
Radioactive Sources
Medical Sources
Consumer Products
Industrial Radiation Sources
Beta Emitter Dose Rates
Positron Emitters
Gamma Exposure Rates
Neutron Exposure Rates
Characteristic Radiations
Thorium-232 & Uranium-238 Decay Chains
SI and US “Traditional” Units
Abbreviations
Conversions
Constants
Units and Terminology
Emergency Response
Risk
Radon
2
2
4
7
7
7
7
11
13
13
24
29
32
33
34
45
48
50
63
64
65
70
71
72
78
79
Medical Treatment for Radiation Exposure
External Exposure Treatment
Inhalation Treatment
Internal Exposure
Ingestion Treatment
Injection Treatment
Absorption Treatment
Acute Radiation Effects
Radioactive Sources
Medical Sources
Consumer Products
Industrial Radiation Sources
Beta Emitter Dose Rates
Positron Emitters
Gamma Exposure Rates
Neutron Exposure Rates
Characteristic Radiations
Thorium-232 & Uranium-238 Decay Chains
SI and US “Traditional” Units
Abbreviations
Conversions
Constants
Units and Terminology
Emergency Response
Risk
Radon
2
2
4
7
7
7
7
11
13
13
24
29
32
33
34
45
48
50
63
64
65
70
71
72
78
79
Medical Treatment for Radiation Exposure
External Exposure Treatment
Inhalation Treatment
Internal Exposure
Ingestion Treatment
Injection Treatment
Absorption Treatment
Acute Radiation Effects
Radioactive Sources
Medical Sources
Consumer Products
Industrial Radiation Sources
Beta Emitter Dose Rates
Positron Emitters
Gamma Exposure Rates
Neutron Exposure Rates
Characteristic Radiations
Thorium-232 & Uranium-238 Decay Chains
SI and US “Traditional” Units
Abbreviations
Conversions
Constants
Units and Terminology
Emergency Response
Risk
Radon
2
2
4
7
7
7
7
11
13
13
24
29
32
33
34
45
48
50
63
64
65
70
71
72
78
79
Author’s notes
Author’s notes
Over my career in health physics starting with a US
Army CBR unit at Dugway Proving Grounds in 1965 I have
needed to quickly find that elusive data point that I just
couldn’t remember, even though I knew the information was in
one of my several hundred reference books.
Over my career in health physics starting with a US
Army CBR unit at Dugway Proving Grounds in 1965 I have
needed to quickly find that elusive data point that I just
couldn’t remember, even though I knew the information was in
one of my several hundred reference books.
So, here it is today, the product of my work to
assemble useful field information from a wide range of
sources.
So, here it is today, the product of my work to
assemble useful field information from a wide range of
sources.
I must give credit to those individuals who put their
efforts into creating the original data. Without their work, this
document could not have been assembled.
I must give credit to those individuals who put their
efforts into creating the original data. Without their work, this
document could not have been assembled.
My family has given me their unlimited support in my
development of this reference book and in my projects all
through my career. Sandy my wife of 30 some years and our
two daughters Susan and Sarah and their excellent husbands,
Bill Gilson and Rolfe Bergstrom, our son-in-laws, continue to
provide me with a steady foundation that allows me to try out
new concepts.
My family has given me their unlimited support in my
development of this reference book and in my projects all
through my career. Sandy my wife of 30 some years and our
two daughters Susan and Sarah and their excellent husbands,
Bill Gilson and Rolfe Bergstrom, our son-in-laws, continue to
provide me with a steady foundation that allows me to try out
new concepts.
James T. (Tom) Voss, NRRPT, CHP
Fellow of the Health Physics Society
Member of the American Nuclear Society
Northern New Mexico, 2013
James T. (Tom) Voss, NRRPT, CHP
Fellow of the Health Physics Society
Member of the American Nuclear Society
Northern New Mexico, 2013
Send your corrections, additions, deletions, and comments to:
Send your corrections, additions, deletions, and comments to:
[email protected]
[email protected]
VOSS-ASSOCIATES.COM
VOSS-ASSOCIATES.COM
Author’s notes
Author’s notes
Over my career in health physics starting with a US
Army CBR unit at Dugway Proving Grounds in 1965 I have
needed to quickly find that elusive data point that I just
couldn’t remember, even though I knew the information was in
one of my several hundred reference books.
Over my career in health physics starting with a US
Army CBR unit at Dugway Proving Grounds in 1965 I have
needed to quickly find that elusive data point that I just
couldn’t remember, even though I knew the information was in
one of my several hundred reference books.
So, here it is today, the product of my work to
assemble useful field information from a wide range of
sources.
So, here it is today, the product of my work to
assemble useful field information from a wide range of
sources.
I must give credit to those individuals who put their
efforts into creating the original data. Without their work, this
document could not have been assembled.
I must give credit to those individuals who put their
efforts into creating the original data. Without their work, this
document could not have been assembled.
My family has given me their unlimited support in my
development of this reference book and in my projects all
through my career. Sandy my wife of 30 some years and our
two daughters Susan and Sarah and their excellent husbands,
Bill Gilson and Rolfe Bergstrom, our son-in-laws, continue to
provide me with a steady foundation that allows me to try out
new concepts.
My family has given me their unlimited support in my
development of this reference book and in my projects all
through my career. Sandy my wife of 30 some years and our
two daughters Susan and Sarah and their excellent husbands,
Bill Gilson and Rolfe Bergstrom, our son-in-laws, continue to
provide me with a steady foundation that allows me to try out
new concepts.
James T. (Tom) Voss, NRRPT, CHP
Fellow of the Health Physics Society
Member of the American Nuclear Society
Northern New Mexico, 20132
James T. (Tom) Voss, NRRPT, CHP
Fellow of the Health Physics Society
Member of the American Nuclear Society
Northern New Mexico, 2013
Send your corrections, additions, deletions, and comments to:
Send your corrections, additions, deletions, and comments to
[email protected]
VOSS-ASSOCIATES.COM
[email protected]
VOSS-ASSOCIATES.COM
How to use this handbook
How to use this handbook
This handbook has sections on external radiation,
surface radioactive contam ination, and airborne
radioactive m aterial. The definitions section will provide
the reader with a clearer understanding of the term s
used in the data presented in this handbook.
This handbook has sections on external radiation,
surface radioactive contam ination, and airborne
radioactive m aterial. The definitions section will provide
the reader with a clearer understanding of the term s
used in the data presented in this handbook.
More in-depth inform ation on specific topics are located
in the other technical Handbooks for Radiation Data,
Radiation Safety, Air Monitoring, & Environm ental Monitoring.
In addition references such as CFRs, ANSI standards, and
governm ent and other publications provide m ore
inform ation. A list of websites in the reference section
provides links to additional resources.
More in-depth inform ation on specific topics are located
in the other technical Handbooks for Radiation Data,
Radiation Safety, Air Monitoring, & Environm ental Monitoring.
In addition references such as CFRs, ANSI standards, and
governm ent and other publications provide m ore
inform ation. A list of websites in the reference section
provides links to additional resources.
In general the term s R, rad, Roentgen, and Rem are
treated as being equivalent in this handbook.
In general the term s R, rad, Roentgen, and Rem are
treated as being equivalent in this handbook.
Gam m a ray constants used in this handbook are stated
for a distance of 30 cm . Other references m ay state
gam m a ray constants for a distance of 1 m eter (100
cm ). Use a conversion factor of 11.11 (100 2/30 2) to
convert from one to the other.
Gam m a ray constants used in this handbook are stated
for a distance of 30 cm . Other references m ay state
gam m a ray constants for a distance of 1 m eter (100
cm ). Use a conversion factor of 11.11 (100 2/30 2) to
convert from one to the other.
How to use this handbook
How to use this handbook
This handbook has sections on external radiation,
surface radioactive contam ination, and airborne
radioactive m aterial. The definitions section will provide
the reader with a clearer understanding of the term s
used in the data presented in this handbook.
This handbook has sections on external radiation,
surface radioactive contam ination, and airborne
radioactive m aterial. The definitions section will provide
the reader with a clearer understanding of the term s
used in the data presented in this handbook.
More in-depth inform ation on specific topics are located
in the other technical Handbooks for Radiation Data,
Radiation Safety, Air Monitoring, & Environm ental Monitoring.
In addition references such as CFRs, ANSI standards, and
governm ent and other publications provide m ore
inform ation. A list of websites in the reference section
provides links to additional resources.
More in-depth inform ation on specific topics are located
in the other technical Handbooks for Radiation Data,
Air Monitoring, & Environm ental Monitoring.
In addition references such as CFRs, ANSI standards, and
governm ent and other publications provide m ore
inform ation. A list of websites in the reference section
provides links to additional resources.
In general the term s R, rad, Roentgen, and Rem are
treated as being equivalent in this handbook.
In general the term s R, rad, Roentgen, and Rem are
treated as being equivalent in this handbook.
Gam m a ray constants used in this handbook are stated
for a distance of 30 cm . Other references m ay state
gam m a ray constants for a distance of 1 m eter (100
cm ). Use a conversion factor of 11.11 (100 2/30 2) to
convert from one to the other.
Gam m a ray constants used in this handbook are stated
for a distance of 30 cm . Other references m ay state
gam m a ray constants for a distance of 1 m eter (100
cm ). Use a conversion factor of 11.11 (100 2/30 2) to
convert from one to the other.
Medical Treatment for Radiation Exposure
External Exposure Treatment
Medical Treatment for Radiation Exposure
External Exposure Treatment
There are several courses of action for m edical
treatm ent of persons exposed to high levels of external
radiation.
There are several courses of action for m edical
treatm ent of persons exposed to high levels of external
radiation.
Anti-oxidants
Anti-oxidants m ay be used to counteract the influence of
free radicals form ed as the result of radiation exposure.
Free radicals react with (and change) body cells.
Vitam ins C and E are com m on treatm ents for reducing
the effects of free radicals. How well this course of
treatm ent m ay work in the case of external radiation
exposure has not been fully evaluated.
Anti-oxidants
Anti-oxidants m ay be used to counteract the influence of
free radicals form ed as the result of radiation exposure.
Free radicals react with (and change) body cells.
Vitam ins C and E are com m on treatm ents for reducing
the effects of free radicals. How well this course of
treatm ent m ay work in the case of external radiation
exposure has not been fully evaluated.
Antibiotics
The use of antibiotics to prevent infection which m ay
occur due to the exposed person’s depressed im m une
system needs to be evaluated carefully before pursuing
this treatm ent. Perhaps m inim izing the sources of
infection would be a better treatm ent process.
Antibiotics
The use of antibiotics to prevent infection which m ay
occur due to the exposed person’s depressed im m une
system needs to be evaluated carefully before pursuing
this treatm ent. Perhaps m inim izing the sources of
infection would be a better treatm ent process.
Blood transfusion
Blood transfusion is used in those cases where the
exposed person’s body cannot replenish the blood cells
rapidly enough.
2
Blood transfusion
Blood transfusion is used in those cases where the
exposed person’s body cannot replenish the blood cells
rapidly enough.
2
Medical Treatment for Radiation Exposure
Medical Treatment for Radiation Exposure
External Exposure Treatment
External Exposure Treatment
There are several courses of action for m edical
treatm ent of persons exposed to high levels of external
radiation.
There are several courses of action for m edical
treatm ent of persons exposed to high levels of external
radiation.
Anti-oxidants
Anti-oxidants m ay be used to counteract the influence of
free radicals form ed as the result of radiation exposure.
Free radicals react with (and change) body cells.
Vitam ins C and E are com m on treatm ents for reducing
the effects of free radicals. How well this course of
treatm ent m ay work in the case of external radiation
exposure has not been fully evaluated.
Anti-oxidants
Anti-oxidants m ay be used to counteract the influence of
free radicals form ed as the result of radiation exposure.
Free radicals react with (and change) body cells.
Vitam ins C and E are com m on treatm ents for reducing
the effects of free radicals. How well this course of
treatm ent m ay work in the case of external radiation
exposure has not been fully evaluated.
Antibiotics
The use of antibiotics to prevent infection which m ay
occur due to the exposed person’s depressed im m une
system needs to be evaluated carefully before pursuing
this treatm ent. Perhaps m inim izing the sources of
infection would be a better treatm ent process.
Antibiotics
The use of antibiotics to prevent infection which m ay
occur due to the exposed person’s depressed im m une
system needs to be evaluated carefully before pursuing
this treatm ent. Perhaps m inim izing the sources of
infection would be a better treatm ent process.
Blood transfusion
Blood transfusion is used in those cases where the
exposed person’s body cannot replenish the blood cells
rapidly enough.
2
Blood transfusion
Blood transfusion is used in those cases where the
exposed person’s body cannot replenish the blood cells
rapidly enough.
2
Bone marrow transplant
Bone marrow transplants are performed when the exposed
person’s bone marrow has been damaged by external
radiation to the extent the marrow can no longer perform its
function of making new cells.
Bone marrow transplant
Bone marrow transplants are performed when the exposed
person’s bone marrow has been damaged by external
radiation to the extent the marrow can no longer perform its
function of making new cells.
The decision to pursue any of these courses of medical
treatment must be carefully considered. Each of the
procedures comes with its own potential negative effects.
However, treatment must be started quickly in order to be
most effective.
The decision to pursue any of these courses of medical
treatment must be carefully considered. Each of the
procedures comes with its own potential negative effects.
However, treatment must be started quickly in order to be
most effective.
Refer to the section on “Acute Radiation Effects” for
symptoms and related hazard levels.
Refer to the section on “Acute Radiation Effects” for
symptoms and related hazard levels.
3
3
Bone marrow transplant
Bone marrow transplants are performed when the exposed
person’s bone marrow has been damaged by external
radiation to the extent the marrow can no longer perform its
function of making new cells.
Bone marrow transplant
Bone marrow transplants are performed when the exposed
person’s bone marrow has been damaged by external
radiation to the extent the marrow can no longer perform its
function of making new cells.
The decision to pursue any of these courses of medical
treatment must be carefully considered. Each of the
procedures comes with its own potential negative effects.
However, treatment must be started quickly in order to be
most effective.
The decision to pursue any of these courses of medical
treatment must be carefully considered. Each of the
procedures comes with its own potential negative effects.
However, treatment must be started quickly in order to be
most effective.
Refer to the section on “Acute Radiation Effects” for
symptoms and related hazard levels.
Refer to the section on “Acute Radiation Effects” for
symptoms and related hazard levels.
3
3
Inhalation Treatment
Inhalation Treatment
There are several courses of action for medical treatment of
persons who have inhaled high levels of contamination.
There are several courses of action for medical treatment of
persons who have inhaled high levels of contamination.
Refer to the section on “Lung Deposition” for clarification of
inhaled particle size related to where in the lung those
particles may be deposited.
Refer to the section on “Lung Deposition” for clarification of
inhaled particle size related to where in the lung those
particles may be deposited.
Anti-oxidants
Anti-oxidants may be used to counteract the influence of free
radicals formed as the result of radiation exposure. Free
radicals react with (and change) body cells. Vitamins C and
E are common treatments for reducing the effects of free
radicals. How well this course of treatment may work in the
case of external radiation exposure has not been fully
evaluated.
Anti-oxidants
Anti-oxidants may be used to counteract the influence of free
radicals formed as the result of radiation exposure. Free
radicals react with (and change) body cells. Vitamins C and
E are common treatments for reducing the effects of free
radicals. How well this course of treatment may work in the
case of external radiation exposure has not been fully
evaluated.
Antibiotics
The use of antibiotics to prevent infection which may occur
due to the exposed person’s depressed immune system
needs to be evaluated carefully before pursuing this
treatment. Perhaps minimizing the sources of infection would
be a better treatment process.
Antibiotics
The use of antibiotics to prevent infection which may occur
due to the exposed person’s depressed immune system
needs to be evaluated carefully before pursuing this
treatment. Perhaps minimizing the sources of infection would
be a better treatment process.
Dilution
Perhaps the most common application of dilution is when an
individual has been exposed to tritium, either thru inhalation,
ingestion, or absorption. Drinking a lot of water will act as a
diuretic and the tritium, which has combined with oxygen to
form tritiated water, will be flushed out of the individual’s
body.
Dilution
Perhaps the most common application of dilution is when an
individual has been exposed to tritium, either thru inhalation,
ingestion, or absorption. Drinking a lot of water will act as a
diuretic and the tritium, which has combined with oxygen to
form tritiated water, will be flushed out of the individual’s
body.
Inhalation Treatment
Inhalation Treatment
There are several courses of action for medical treatment of
persons who have inhaled high levels of contamination.
There are several courses of action for medical treatment of
persons who have inhaled high levels of contamination.
Refer to the section on “Lung Deposition” for clarification of
inhaled particle size related to where in the lung those
particles may be deposited.
Refer to the section on “Lung Deposition” for clarification of
inhaled particle size related to where in the lung those
particles may be deposited.
Anti-oxidants
Anti-oxidants may be used to counteract the influence of free
radicals formed as the result of radiation exposure. Free
radicals react with (and change) body cells. Vitamins C and
E are common treatments for reducing the effects of free
radicals. How well this course of treatment may work in the
case of external radiation exposure has not been fully
evaluated.
Anti-oxidants
Anti-oxidants may be used to counteract the influence of free
radicals formed as the result of radiation exposure. Free
radicals react with (and change) body cells. Vitamins C and
E are common treatments for reducing the effects of free
radicals. How well this course of treatment may work in the
case of external radiation exposure has not been fully
evaluated.
Antibiotics
The use of antibiotics to prevent infection which may occur
due to the exposed person’s depressed immune system
needs to be evaluated carefully before pursuing this
treatment. Perhaps minimizing the sources of infection would
be a better treatment process.
Antibiotics
The use of antibiotics to prevent infection which may occur
due to the exposed person’s depressed immune system
needs to be evaluated carefully before pursuing this
treatment. Perhaps minimizing the sources of infection would
be a better treatment process.
Dilution
Perhaps the most common application of dilution is when an
individual has been exposed to tritium, either thru inhalation,
ingestion, or absorption. Drinking a lot of water will act as a
diuretic and the tritium, which has combined with oxygen to
form tritiated water, will be flushed out of the individual’s
body.
Dilution
Perhaps the most common application of dilution is when an
individual has been exposed to tritium, either thru inhalation,
ingestion, or absorption. Drinking a lot of water will act as a
diuretic and the tritium, which has combined with oxygen to
form tritiated water, will be flushed out of the individual’s
body.
Substitution
The most recognizable application of substitution is the
administration of potassium iodide to individuals who may be
exposed to radioactive iodine. If the potassium iodide is
administered before the potential intake then the thyroid will
take up that iodine and not the radioactive iodine. If the
potassium iodine is administered after the radioactive iodine
intake then the non-radioactive iodine displaces the
radioactive iodine to some extent.
Substitution
The most recognizable application of substitution is the
administration of potassium iodide to individuals who may be
exposed to radioactive iodine. If the potassium iodide is
administered before the potential intake then the thyroid will
take up that iodine and not the radioactive iodine. If the
potassium iodine is administered after the radioactive iodine
intake then the non-radioactive iodine displaces the
radioactive iodine to some extent.
Chelation
Chelation has proven successful for both radioactive and
non-radioactive metals. Chelating agents similar to EDTA
(ethylene diamine tetra-acetic acid) are used to make the
radioactive metals in the exposed individual’s body more
soluble so they can be eliminated more efficiently by the
body’s mechanisms. For transuranic intakes chelation is
most effective if administered within one hour of the intake.
In those cases chelation has proven to remove as much as
90% of the radioactive material originally taken into the
individual’s body.
Chelation
Chelation has proven successful for both radioactive and
non-radioactive metals. Chelating agents similar to EDTA
(ethylene diamine tetra-acetic acid) are used to make the
radioactive metals in the exposed individual’s body more
soluble so they can be eliminated more efficiently by the
body’s mechanisms. For transuranic intakes chelation is
most effective if administered within one hour of the intake.
In those cases chelation has proven to remove as much as
90% of the radioactive material originally taken into the
individual’s body.
Lung Lavage
Lung lavage is a somewhat extreme medical procedure and
the patient must be in good physical condition. However lung
lavage has proven to be effective in removing small particles
from the lungs of individuals incases such as coal miners or
heavy tobacco smokers. In the medical procedure one lung
is collapsed then filled with water (in the case of radioactive
metals the water may contain a chelating agent) then the
patient is gently rocked to get the water more deeply into the
lung. The water is removed and the lung is re-inflated with
air. Then the same process is performed on the second lung.
Lung Lavage
Lung lavage is a somewhat extreme medical procedure and
the patient must be in good physical condition. However lung
lavage has proven to be effective in removing small particles
from the lungs of individuals incases such as coal miners or
heavy tobacco smokers. In the medical procedure one lung
is collapsed then filled with water (in the case of radioactive
metals the water may contain a chelating agent) then the
patient is gently rocked to get the water more deeply into the
lung. The water is removed and the lung is re-inflated with
air. Then the same process is performed on the second lung.
Substitution
The most recognizable application of substitution is the
administration of potassium iodide to individuals who may be
exposed to radioactive iodine. If the potassium iodide is
administered before the potential intake then the thyroid will
take up that iodine and not the radioactive iodine. If the
potassium iodine is administered after the radioactive iodine
intake then the non-radioactive iodine displaces the
radioactive iodine to some extent.
Substitution
The most recognizable application of substitution is the
administration of potassium iodide to individuals who may be
exposed to radioactive iodine. If the potassium iodide is
administered before the potential intake then the thyroid will
take up that iodine and not the radioactive iodine. If the
potassium iodine is administered after the radioactive iodine
intake then the non-radioactive iodine displaces the
radioactive iodine to some extent.
Chelation
Chelation has proven successful for both radioactive and
non-radioactive metals. Chelating agents similar to EDTA
(ethylene diamine tetra-acetic acid) are used to make the
radioactive metals in the exposed individual’s body more
soluble so they can be eliminated more efficiently by the
body’s mechanisms. For transuranic intakes chelation is
most effective if administered within one hour of the intake.
In those cases chelation has proven to remove as much as
90% of the radioactive material originally taken into the
individual’s body.
Chelation
Chelation has proven successful for both radioactive and
non-radioactive metals. Chelating agents similar to EDTA
(ethylene diamine tetra-acetic acid) are used to make the
radioactive metals in the exposed individual’s body more
soluble so they can be eliminated more efficiently by the
body’s mechanisms. For transuranic intakes chelation is
most effective if administered within one hour of the intake.
In those cases chelation has proven to remove as much as
90% of the radioactive material originally taken into the
individual’s body.
Lung Lavage
Lung lavage is a somewhat extreme medical procedure and
the patient must be in good physical condition. However lung
lavage has proven to be effective in removing small particles
from the lungs of individuals incases such as coal miners or
heavy tobacco smokers. In the medical procedure one lung
is collapsed then filled with water (in the case of radioactive
metals the water may contain a chelating agent) then the
patient is gently rocked to get the water more deeply into the
lung. The water is removed and the lung is re-inflated with
air. Then the same process is performed on the second lung.
Lung Lavage
Lung lavage is a somewhat extreme medical procedure and
the patient must be in good physical condition. However lung
lavage has proven to be effective in removing small particles
from the lungs of individuals incases such as coal miners or
heavy tobacco smokers. In the medical procedure one lung
is collapsed then filled with water (in the case of radioactive
metals the water may contain a chelating agent) then the
patient is gently rocked to get the water more deeply into the
lung. The water is removed and the lung is re-inflated with
air. Then the same process is performed on the second lung.
Lung Deposition from ICRP 30
AMAD
:
(microns)
0.1
1
10
NP
Nasopharanx
0.01
0.3
0.9
TB
Tracheabronchus
0.08
0.08
0.08
Lung Deposition from ICRP 30
AMAD
:
Alveolar
0.61
0.25
0.04
(microns)
0.1
1
10
Naso-Pharyngeal
NP
Nasopharanx
0.01
0.3
0.9
TB
Tracheabronchus
0.08
0.08
0.08
Alveolar
0.61
0.25
0.04
Naso-Pharyngeal
Regions of
Deposition
Regions of
Deposition
Tracheobronchial
Tracheobronchial
Alveolar
Alveolar
AMAD is Activity Median Aerodynamic Diameter, the
apparent diameter of a particle in terms of how the particle
behaves in an air stream.
1 micron (:) is 1E-6 meters (2.54E-8 inches); a 100 micron
diameter particle is barely visible with the naked eye.
AMAD is Activity Median Aerodynamic Diameter, the
apparent diameter of a particle in terms of how the particle
behaves in an air stream.
1 micron (:) is 1E-6 meters (2.54E-8 inches); a 100 micron
diameter particle is barely visible with the naked eye.
The smaller particles will tend to penetrate to the alveolar
section of the lungs, the area of the lungs where oxygen
transfers into the blood stream and carbon dioxide transfers
out of the blood stream.
The smaller particles will tend to penetrate to the alveolar
section of the lungs, the area of the lungs where oxygen
transfers into the blood stream and carbon dioxide transfers
out of the blood stream.
Lung Deposition from ICRP 30
AMAD
:
(microns)
0.1
1
10
NP
Nasopharanx
0.01
0.3
0.9
TB
Tracheabronchus
0.08
0.08
0.08
Lung Deposition from ICRP 30
AMAD
:
Alveolar
0.61
0.25
0.04
(microns)
0.1
1
10
Naso-Pharyngeal
Regions of
Deposition
NP
Nasopharanx
0.01
0.3
0.9
TB
Tracheabronchus
0.08
0.08
0.08
Alveolar
0.61
0.25
0.04
Naso-Pharyngeal
Regions of
Deposition
Tracheobronchial
Tracheobronchial
Alveolar
Alveolar
AMAD is Activity Median Aerodynamic Diameter, the
apparent diameter of a particle in terms of how the particle
behaves in an air stream.
1 micron (:) is 1E-6 meters (2.54E-8 inches); a 100 micron
diameter particle is barely visible with the naked eye.
AMAD is Activity Median Aerodynamic Diameter, the
apparent diameter of a particle in terms of how the particle
behaves in an air stream.
1 micron (:) is 1E-6 meters (2.54E-8 inches); a 100 micron
diameter particle is barely visible with the naked eye.
The smaller particles will tend to penetrate to the alveolar
section of the lungs, the area of the lungs where oxygen
transfers into the blood stream and carbon dioxide transfers
out of the blood stream.
The smaller particles will tend to penetrate to the alveolar
section of the lungs, the area of the lungs where oxygen
transfers into the blood stream and carbon dioxide transfers
out of the blood stream.
Internal Exposure
Refer to 10CFR20 and 10CFR835 regulations for “Ingestion
ALIs” for Ingestion, Injection, and Absorption and “Inhalation
DACs” for Inhalation of Airborne Radioactive Material.
Ingestion Treatment
Internal Exposure
Refer to 10CFR20 and 10CFR835 regulations for “Ingestion
ALIs” for Ingestion, Injection, and Absorption and “Inhalation
DACs” for Inhalation of Airborne Radioactive Material.
Ingestion Treatment
There are several courses of action for medical treatment of
persons who have ingested high levels of contamination.
There are several courses of action for medical treatment of
persons who have ingested high levels of contamination.
Anti-oxidants, Antibiotics, Dilution, Substitution, and
Chelation may be effective in minimizing the effect of
ingestion of radioactive contamination.
Anti-oxidants, Antibiotics, Dilution, Substitution, and
Chelation may be effective in minimizing the effect of
ingestion of radioactive contamination.
Injection Treatment
Excision
Excision is the first action taken in the event of an
individual getting a piece of radioactive material into
their skin. Following that the other courses of action;
Anti-oxidants, Antibiotics, Dilution, Substitution, and
Chelation may be effective in minimizing the effect of
ingestion of radioactive contamination. A specialized
radiation detector known as a “wound counter” is used to
assist the surgeon in determining how much tissue must be
removed.
Absorption Treatment
Dilution
Tritium is the most commonly absorbed radioactive
material. Dilution by drinking lots of water is the most
effective method of reducing the effect of tritium
absorption.
Internal Exposure
Refer to 10CFR20 and 10CFR835 regulations for “Ingestion
ALIs” for Ingestion, Injection, and Absorption and “Inhalation
DACs” for Inhalation of Airborne Radioactive Material.
Ingestion Treatment
Injection Treatment
Excision
Excision is the first action taken in the event of an
individual getting a piece of radioactive material into
their skin. Following that the other courses of action;
Anti-oxidants, Antibiotics, Dilution, Substitution, and
Chelation may be effective in minimizing the effect of
ingestion of radioactive contamination. A specialized
radiation detector known as a “wound counter” is used to
assist the surgeon in determining how much tissue must be
removed.
Absorption Treatment
Dilution
Tritium is the most commonly absorbed radioactive
material. Dilution by drinking lots of water is the most
effective method of reducing the effect of tritium
absorption.
Internal Exposure
Refer to 10CFR20 and 10CFR835 regulations for “Ingestion
ALIs” for Ingestion, Injection, and Absorption and “Inhalation
DACs” for Inhalation of Airborne Radioactive Material.
Ingestion Treatment
There are several courses of action for medical treatment of
persons who have ingested high levels of contamination.
There are several courses of action for medical treatment of
persons who have ingested high levels of contamination.
Anti-oxidants, Antibiotics, Dilution, Substitution, and
Chelation may be effective in minimizing the effect of
ingestion of radioactive contamination.
Anti-oxidants, Antibiotics, Dilution, Substitution, and
Chelation may be effective in minimizing the effect of
ingestion of radioactive contamination.
Injection Treatment
Excision
Excision is the first action taken in the event of an
individual getting a piece of radioactive material into
their skin. Following that the other courses of action;
Anti-oxidants, Antibiotics, Dilution, Substitution, and
Chelation may be effective in minimizing the effect of
ingestion of radioactive contamination. A specialized
radiation detector known as a “wound counter” is used to
assist the surgeon in determining how much tissue must be
removed.
Absorption Treatment
Dilution
Tritium is the most commonly absorbed radioactive
material. Dilution by drinking lots of water is the most
effective method of reducing the effect of tritium
absorption.
Injection Treatment
Excision
Excision is the first action taken in the event of an
individual getting a piece of radioactive material into
their skin. Following that the other courses of action;
Anti-oxidants, Antibiotics, Dilution, Substitution, and
Chelation may be effective in minimizing the effect of
ingestion of radioactive contamination. A specialized
radiation detector known as a “wound counter” is used to
assist the surgeon in determining how much tissue must be
removed.
Absorption Treatment
Dilution
Tritium is the most commonly absorbed radioactive
material. Dilution by drinking lots of water is the most
effective method of reducing the effect of tritium
absorption.
Relative Hazards of External, Inhaled,
Injected, and Ingested Radioactivity
Relative Hazards of External, Inhaled,
Injected, and Ingested Radioactivity
External Radiation
Refer to the section on “Acute Radiation Effects” for
symptoms and related hazard levels.
External Radiation
Refer to the section on “Acute Radiation Effects” for
symptoms and related hazard levels.
In addition, for high levels of absorbed neutron radiation from
a criticality incident an immediate measurement of the
sodium-24 in the patient’s body by using a gamma detector
can provide a quick estimate of the patient’s absorbed dose.
In addition, for high levels of absorbed neutron radiation from
a criticality incident an immediate measurement of the
sodium-24 in the patient’s body by using a gamma detector
can provide a quick estimate of the patient’s absorbed dose.
Inhaled Radioactivity
Refer to the section on “Lung Deposition” for clarification of
inhaled particle size related to where in the lung those
particles may be deposited. Refer to 10CFR20 and
10CFR835 regulations regarding “inhalation DACs” for further
clarification on the relative hazards of inhalation of radioactive
materials.
Inhaled Radioactivity
Refer to the section on “Lung Deposition” for clarification of
inhaled particle size related to where in the lung those
particles may be deposited. Refer to 10CFR20 and
10CFR835 regulations regarding “inhalation DACs” for further
clarification on the relative hazards of inhalation of radioactive
materials.
The smallest particles which penetrate into the alveolar
section of the lung present the greater hazard. Those smaller
particles can transfer to the blood stream at that point and
can then travel throughout the body.
The smallest particles which penetrate into the alveolar
section of the lung present the greater hazard. Those smaller
particles can transfer to the blood stream at that point and
can then travel throughout the body.
Two measurement techniques provide a quick estimate of the
amount of inhaled radioactivity. One is known as a nose
swipe, which is simply using something like a Q-tip to swipe
around the inside of the nose, then counting the radioactivity
on the Q-tip. A second measurement technique is to perform
a “chest count” which is using a high efficiency gamma
detector to identify the radio-nuclide and measure its activity.
Two measurement techniques provide a quick estimate of the
amount of inhaled radioactivity. One is known as a nose
swipe, which is simply using something like a Q-tip to swipe
around the inside of the nose, then counting the radioactivity
on the Q-tip. A second measurement technique is to perform
a “chest count” which is using a high efficiency gamma
detector to identify the radio-nuclide and measure its activity.
Relative Hazards of External, Inhaled,
Injected, and Ingested Radioactivity
Relative Hazards of External, Inhaled,
Injected, and Ingested Radioactivity
External Radiation
Refer to the section on “Acute Radiation Effects” for
symptoms and related hazard levels.
External Radiation
Refer to the section on “Acute Radiation Effects” for
symptoms and related hazard levels.
In addition, for high levels of absorbed neutron radiation from
a criticality incident an immediate measurement of the
sodium-24 in the patient’s body by using a gamma detector
can provide a quick estimate of the patient’s absorbed dose.
In addition, for high levels of absorbed neutron radiation from
a criticality incident an immediate measurement of the
sodium-24 in the patient’s body by using a gamma detector
can provide a quick estimate of the patient’s absorbed dose.
Inhaled Radioactivity
Refer to the section on “Lung Deposition” for clarification of
inhaled particle size related to where in the lung those
particles may be deposited. Refer to 10CFR20 and
10CFR835 regulations regarding “inhalation DACs” for further
clarification on the relative hazards of inhalation of radioactive
materials.
Inhaled Radioactivity
Refer to the section on “Lung Deposition” for clarification of
inhaled particle size related to where in the lung those
particles may be deposited. Refer to 10CFR20 and
10CFR835 regulations regarding “inhalation DACs” for further
clarification on the relative hazards of inhalation of radioactive
materials.
The smallest particles which penetrate into the alveolar
section of the lung present the greater hazard. Those smaller
particles can transfer to the blood stream at that point and
can then travel throughout the body.
The smallest particles which penetrate into the alveolar
section of the lung present the greater hazard. Those smaller
particles can transfer to the blood stream at that point and
can then travel throughout the body.
Two measurement techniques provide a quick estimate of the
amount of inhaled radioactivity. One is known as a nose
swipe, which is simply using something like a Q-tip to swipe
around the inside of the nose, then counting the radioactivity
on the Q-tip. A second measurement technique is to perform
a “chest count” which is using a high efficiency gamma
detector to identify the radio-nuclide and measure its activity.
Two measurement techniques provide a quick estimate of the
amount of inhaled radioactivity. One is known as a nose
swipe, which is simply using something like a Q-tip to swipe
around the inside of the nose, then counting the radioactivity
on the Q-tip. A second measurement technique is to perform
a “chest count” which is using a high efficiency gamma
detector to identify the radio-nuclide and measure its activity.
Injected Radioactivity
Injected radioactivity is that caused by a radioactively
contaminated item or a piece of radioactive material
penetrating into tissue. Some of the radioactive material may
remain in the wound after the object is removed.
Injected Radioactivity
Injected radioactivity is that caused by a radioactively
contaminated item or a piece of radioactive material
penetrating into tissue. Some of the radioactive material may
remain in the wound after the object is removed.
A quick estimate of the amount of radioactivity remaining in
the wound can be made by using a hand-held radiation
detector, one that is capable of measuring the type of
radiation (alpha, beta, or gamma).
A quick estimate of the amount of radioactivity remaining in
the wound can be made by using a hand-held radiation
detector, one that is capable of measuring the type of
radiation (alpha, beta, or gamma).
A second measurement technique is to perform a “wound
count” which is using a high efficiency gamma detector to
identify the radio-nuclide and if the radioactive material has
more than one photon emission energy to determine the
depth in the tissue and the radioactive material’s activity.
A second measurement technique is to perform a “wound
count” which is using a high efficiency gamma detector to
identify the radio-nuclide and if the radioactive material has
more than one photon emission energy to determine the
depth in the tissue and the radioactive material’s activity.
Physical and Chemical Form
Physical and Chemical Form
Physical Form
The physical form of radioactive material may be as a gas,
liquid, or solid. Gas is the most mobile while a solid is the
least mobile. Both liquid and solid physical forms may exist in
different particle sizes. Aerosols generally refer to physical
forms that are very mobile due to being a gas or very small
liquid or solid particles. Particles sizes smaller than 10
microns ( 2.54E-7 inches) in diameter can easily become
airborne. However, particles with a high specific gravity will
be less mobile. Particle sizes smaller than 5 microns are of
greater concern than larger particles due to their greater
mobility.
Physical Form
The physical form of radioactive material may be as a gas,
liquid, or solid. Gas is the most mobile while a solid is the
least mobile. Both liquid and solid physical forms may exist in
different particle sizes. Aerosols generally refer to physical
forms that are very mobile due to being a gas or very small
liquid or solid particles. Particles sizes smaller than 10
microns ( 2.54E-7 inches) in diameter can easily become
airborne. However, particles with a high specific gravity will
be less mobile. Particle sizes smaller than 5 microns are of
greater concern than larger particles due to their greater
mobility.
Injected Radioactivity
Injected radioactivity is that caused by a radioactively
contaminated item or a piece of radioactive material
penetrating into tissue. Some of the radioactive material may
remain in the wound after the object is removed.
Injected Radioactivity
Injected radioactivity is that caused by a radioactively
contaminated item or a piece of radioactive material
penetrating into tissue. Some of the radioactive material may
remain in the wound after the object is removed.
A quick estimate of the amount of radioactivity remaining in
the wound can be made by using a hand-held radiation
detector, one that is capable of measuring the type of
radiation (alpha, beta, or gamma).
A quick estimate of the amount of radioactivity remaining in
the wound can be made by using a hand-held radiation
detector, one that is capable of measuring the type of
radiation (alpha, beta, or gamma).
A second measurement technique is to perform a “wound
count” which is using a high efficiency gamma detector to
identify the radio-nuclide and if the radioactive material has
more than one photon emission energy to determine the
depth in the tissue and the radioactive material’s activity.
A second measurement technique is to perform a “wound
count” which is using a high efficiency gamma detector to
identify the radio-nuclide and if the radioactive material has
more than one photon emission energy to determine the
depth in the tissue and the radioactive material’s activity.
Physical and Chemical Form
Physical and Chemical Form
Physical Form
The physical form of radioactive material may be as a gas,
liquid, or solid. Gas is the most mobile while a solid is the
least mobile. Both liquid and solid physical forms may exist in
different particle sizes. Aerosols generally refer to physical
forms that are very mobile due to being a gas or very small
liquid or solid particles. Particles sizes smaller than 10
microns ( 2.54E-7 inches) in diameter can easily become
airborne. However, particles with a high specific gravity will
be less mobile. Particle sizes smaller than 5 microns are of
greater concern than larger particles due to their greater
mobility.
Physical Form
The physical form of radioactive material may be as a gas,
liquid, or solid. Gas is the most mobile while a solid is the
least mobile. Both liquid and solid physical forms may exist in
different particle sizes. Aerosols generally refer to physical
forms that are very mobile due to being a gas or very small
liquid or solid particles. Particles sizes smaller than 10
microns ( 2.54E-7 inches) in diameter can easily become
airborne. However, particles with a high specific gravity will
be less mobile. Particle sizes smaller than 5 microns are of
greater concern than larger particles due to their greater
mobility.
Chemical Form
The chemical form of radioactive material determines how
easily that radioactive material is taken into the body and how
widespread it will become in the body. The less soluble
chemical forms are generally less of a hazard once they are
in the body than the more soluble chemical forms. However,
the less soluble chemical forms tend to remain in the body for
a longer period of time than the more soluble chemical forms.
The chemical form of the radioactive material can change
once it is in the body due to simple chemical reactions.
Further, specific chemical forms tend to become attracted to
different tissues in the body, such as the radioactive material
collecting on bone or collecting in the blood or other tissues.
Radioactive material in the body is routinely excreted from the
body through feces, urine, and other bodily excretions. This
excretion can be speeded up by various methods such as
dilution, substitution, and chelation.
Chemical Form
The chemical form of radioactive material determines how
easily that radioactive material is taken into the body and how
widespread it will become in the body. The less soluble
chemical forms are generally less of a hazard once they are
in the body than the more soluble chemical forms. However,
the less soluble chemical forms tend to remain in the body for
a longer period of time than the more soluble chemical forms.
The chemical form of the radioactive material can change
once it is in the body due to simple chemical reactions.
Further, specific chemical forms tend to become attracted to
different tissues in the body, such as the radioactive material
collecting on bone or collecting in the blood or other tissues.
Radioactive material in the body is routinely excreted from the
body through feces, urine, and other bodily excretions. This
excretion can be speeded up by various methods such as
dilution, substitution, and chelation.
Physical, Biological, and Effective Half-life
Physical, Biological, and Effective Half-life
Physical half-life is the radioactive half-life of the material.
Biological half-life refers to how long the radioactive material
will remain in the body under normal circumstances. Effective
half-life is combination of physical and biological half-life.
Consider a long-lived radio-nuclide such as plutonium-239
with a physical half-life of 24,000 years. The biological halflife of plutonium-239 is from a few years to near 24,000 years
depending on the chemical form of the plutonium-239. That
biological half-life can be shortened by the use of a chelating
agent that combines with the plutonium-239 and makes it
more soluble which shortens the effective half-life to the
extent that >90% of the plutonium-239 is gone in 1 year.
Physical half-life is the radioactive half-life of the material.
Biological half-life refers to how long the radioactive material
will remain in the body under normal circumstances. Effective
half-life is combination of physical and biological half-life.
Consider a long-lived radio-nuclide such as plutonium-239
with a physical half-life of 24,000 years. The biological halflife of plutonium-239 is from a few years to near 24,000 years
depending on the chemical form of the plutonium-239. That
biological half-life can be shortened by the use of a chelating
agent that combines with the plutonium-239 and makes it
more soluble which shortens the effective half-life to the
extent that >90% of the plutonium-239 is gone in 1 year.
Chemical Form
The chemical form of radioactive material determines how
easily that radioactive material is taken into the body and how
widespread it will become in the body. The less soluble
chemical forms are generally less of a hazard once they are
in the body than the more soluble chemical forms. However,
the less soluble chemical forms tend to remain in the body for
a longer period of time than the more soluble chemical forms.
The chemical form of the radioactive material can change
once it is in the body due to simple chemical reactions.
Further, specific chemical forms tend to become attracted to
different tissues in the body, such as the radioactive material
collecting on bone or collecting in the blood or other tissues.
Radioactive material in the body is routinely excreted from the
body through feces, urine, and other bodily excretions. This
excretion can be speeded up by various methods such as
dilution, substitution, and chelation.
Chemical Form
The chemical form of radioactive material determines how
easily that radioactive material is taken into the body and how
widespread it will become in the body. The less soluble
chemical forms are generally less of a hazard once they are
in the body than the more soluble chemical forms. However,
the less soluble chemical forms tend to remain in the body for
a longer period of time than the more soluble chemical forms.
The chemical form of the radioactive material can change
once it is in the body due to simple chemical reactions.
Further, specific chemical forms tend to become attracted to
different tissues in the body, such as the radioactive material
collecting on bone or collecting in the blood or other tissues.
Radioactive material in the body is routinely excreted from the
body through feces, urine, and other bodily excretions. This
excretion can be speeded up by various methods such as
dilution, substitution, and chelation.
Physical, Biological, and Effective Half-life
Physical, Biological, and Effective Half-life
Physical half-life is the radioactive half-life of the material.
Biological half-life refers to how long the radioactive material
will remain in the body under normal circumstances. Effective
half-life is combination of physical and biological half-life.
Consider a long-lived radio-nuclide such as plutonium-239
with a physical half-life of 24,000 years. The biological halflife of plutonium-239 is from a few years to near 24,000 years
depending on the chemical form of the plutonium-239. That
biological half-life can be shortened by the use of a chelating
agent that combines with the plutonium-239 and makes it
more soluble which shortens the effective half-life to the
extent that >90% of the plutonium-239 is gone in 1 year.
Physical half-life is the radioactive half-life of the material.
Biological half-life refers to how long the radioactive material
will remain in the body under normal circumstances. Effective
half-life is combination of physical and biological half-life.
Consider a long-lived radio-nuclide such as plutonium-239
with a physical half-life of 24,000 years. The biological halflife of plutonium-239 is from a few years to near 24,000 years
depending on the chemical form of the plutonium-239. That
biological half-life can be shortened by the use of a chelating
agent that combines with the plutonium-239 and makes it
more soluble which shortens the effective half-life to the
extent that >90% of the plutonium-239 is gone in 1 year.
ACUTE RADIATION EFFECTS
ACUTE RADIATION EFFECTS
0 – 25 REM (0 - 0.25 Sv)
minimal decrease in white blood cell count for ~ 2weeks
increase in risk of dying from cancer from US average risk of
~ 14 persons per 100 population to ~ 17 persons per 100
population (3 additional persons per 100 population will
experience the onset of terminal cancer ~25 years after the
acute exposure)
0 – 25 REM (0 - 0.25 Sv)
minimal decrease in white blood cell count for ~ 2weeks
increase in risk of dying from cancer from US average risk of
~ 14 persons per 100 population to ~ 17 persons per 100
population (3 additional persons per 100 population will
experience the onset of terminal cancer ~25 years after the
acute exposure)
> 25 REM - < 100 REM (0.25 - 1 Sv)
small decrease in white blood cell count for > 2 weeks
increase in risk of dying from cancer to ~ 26 in 100
> 25 REM - < 100 REM (0.25 - 1 Sv)
small decrease in white blood cell count for > 2 weeks
increase in risk of dying from cancer to ~ 26 in 100
> 100 REM - < 200 REM (1 - 2 Sv)
moderate decrease in white blood cell count
25% of those exposed will experience nausea within a few
hours
less than 5% of those exposed require hospitalization
increase in risk of dying from cancer to ~ 38 in 100
> 100 REM - < 200 REM (1 - 2 Sv)
moderate decrease in white blood cell count
25% of those exposed will experience nausea within a few
hours
less than 5% of those exposed require hospitalization
increase in risk of dying from cancer to ~ 38 in 100
> 200 REM - < 600 REM (2 - 6 Sv)
major decrease in white blood cell count
~ 100% of those exposed will experience nausea within a few
hours
appearance of bruises on skin (purpura)
pneumonia symptoms
hair loss
90% of those exposed require hospitalization
decrease in thinking ability for ~ 2 weeks
increase in risk of dying from cancer to ~ 74 in 100
11
> 200 REM - < 600 REM (2 - 6 Sv)
major decrease in white blood cell count
~ 100% of those exposed will experience nausea within a few
hours
appearance of bruises on skin (purpura)
pneumonia symptoms
hair loss
90% of those exposed require hospitalization
decrease in thinking ability for ~ 2 weeks
increase in risk of dying from cancer to ~ 74 in 100
11
ACUTE RADIATION EFFECTS
ACUTE RADIATION EFFECTS
0 – 25 REM (0 - 0.25 Sv)
minimal decrease in white blood cell count for ~ 2weeks
increase in risk of dying from cancer from US average risk of
~ 14 persons per 100 population to ~ 17 persons per 100
population (3 additional persons per 100 population will
experience the onset of terminal cancer ~25 years after the
acute exposure)
0 – 25 REM (0 - 0.25 Sv)
minimal decrease in white blood cell count for ~ 2weeks
increase in risk of dying from cancer from US average risk of
~ 14 persons per 100 population to ~ 17 persons per 100
population (3 additional persons per 100 population will
experience the onset of terminal cancer ~25 years after the
acute exposure)
> 25 REM - < 100 REM (0.25 - 1 Sv)
small decrease in white blood cell count for > 2 weeks
increase in risk of dying from cancer to ~ 26 in 100
> 25 REM - < 100 REM (0.25 - 1 Sv)
small decrease in white blood cell count for > 2 weeks
increase in risk of dying from cancer to ~ 26 in 100
> 100 REM - < 200 REM (1 - 2 Sv)
moderate decrease in white blood cell count
25% of those exposed will experience nausea within a few
hours
less than 5% of those exposed require hospitalization
increase in risk of dying from cancer to ~ 38 in 100
> 100 REM - < 200 REM (1 - 2 Sv)
moderate decrease in white blood cell count
25% of those exposed will experience nausea within a few
hours
less than 5% of those exposed require hospitalization
increase in risk of dying from cancer to ~ 38 in 100
> 200 REM - < 600 REM (2 - 6 Sv)
major decrease in white blood cell count
~ 100% of those exposed will experience nausea within a few
hours
appearance of bruises on skin (purpura)
pneumonia symptoms
hair loss
90% of those exposed require hospitalization
decrease in thinking ability for ~ 2 weeks
increase in risk of dying from cancer to ~ 74 in 100
11
> 200 REM - < 600 REM (2 -6 Sv)
major decrease in white blood cell count
~ 100% of those exposed will experience nausea within a few
hours
appearance of bruises on skin (purpura)
pneumonia symptoms
hair loss
90% of those exposed require hospitalization
decrease in thinking ability for ~ 2 weeks
increase in risk of dying from cancer to ~ 74 in 100
11
600 REM - < 800 REM (6 - 8 Sv)
all of the above symptoms will be present
100% of those exposed require hospitalization
~ 100% of those exposed will die within a few weeks
without medical treatment
increase in risk of dying from cancer to ~ 98 in 100
600 REM - < 800 REM (6 - 8 Sv)
all of the above symptoms will be present
100% of those exposed require hospitalization
~ 100% of those exposed will die within a few weeks
without medical treatment
increase in risk of dying from cancer to ~ 98 in 100
800 REM - < 2000 REM (8 - 20 Sv)
all of the above symptoms will be present
diarrhea, fever, electrolytes imbalance, GI tract and
respiratory system failure
100% of those exposed will be incapacitated within hours
very few of those exposed will survive
800 REM - < 2000 REM (8 - 20 Sv)
all of the above symptoms will be present
diarrhea, fever, electrolytes imbalance, GI tract and
respiratory system failure
100% of those exposed will be incapacitated within hours
very few of those exposed will survive
> 2000 REM (> 20 Sv)
100% mortality within a few days
> 2000 REM (> 20 Sv)
100% mortality within a few days
Lymphocyte - white blood cells
Leukopenia - abnormally low white blood cell count
Purpura - purple discoloration of skin caused by blood
bleeding into the skin tissue
Pneumonia - inflammation of lung tissue, accompanied by
fever, chills, cough, and difficulty in breathing
Hematopoietic – decrease in the formation of blood cells
Ataxia - inability to coordinate voluntary muscular
movements
BEIR V 1990 800 excess deaths per 100,000 persons at 10
rem (0.1 Sv)
4,000 Hiroshima survivors in excess of 50 rem dose had an
extra 300 incidences of cancer
( ~ 7500 excess deaths per 100,000 at 50 rem) (0.5 Sv)
( ~ 1500 excess deaths per 100,000 at 10 rem) (0.1 Sv)
Lymphocyte - white blood cells
Leukopenia - abnormally low white blood cell count
Purpura - purple discoloration of skin caused by blood
bleeding into the skin tissue
Pneumonia - inflammation of lung tissue, accompanied by
fever, chills, cough, and difficulty in breathing
Hematopoietic – decrease in the formation of blood cells
Ataxia - inability to coordinate voluntary muscular
movements
BEIR V 1990 800 excess deaths per 100,000 persons at 10
rem (0.1 Sv)
4,000 Hiroshima survivors in excess of 50 rem dose had an
extra 300 incidences of cancer
( ~ 7500 excess deaths per 100,000 at 50 rem) (0.5 Sv)
( ~ 1500 excess deaths per 100,000 at 10 rem) (
600 REM - < 800 REM (6 - 8 Sv)
all of the above symptoms will be present
100% of those exposed require hospitalization
~ 100% of those exposed will die within a few weeks
without medical treatment
increase in risk of dying from cancer to ~ 98 in 100
600 REM - < 800 REM (6 - 8 Sv)
all of the above symptoms will be present
100% of those exposed require hospitalization
~ 100% of those exposed will die within a few weeks
without medical treatment
increase in risk of dying from cancer to ~ 98 in 100
800 REM - < 2000 REM (8 - 20 Sv)
all of the above symptoms will be present
diarrhea, fever, electrolytes imbalance, GI tract and
respiratory system failure
100% of those exposed will be incapacitated within hours
very few of those exposed will survive
800 REM - < 2000 REM (8 - 20 Sv)
all of the above symptoms will be present
diarrhea, fever, electrolytes imbalance, GI tract and
respiratory system failure
100% of those exposed will be incapacitated within hours
very few of those exposed will survive
> 2000 REM (> 20 Sv)
100% mortality within a few days
> 2000 REM (> 20 Sv)
100% mortality within a few days
Lymphocyte - white blood cells
Leukopenia - abnormally low white blood cell count
Purpura - purple discoloration of skin caused by blood
bleeding into the skin tissue
Pneumonia - inflammation of lung tissue, accompanied by
fever, chills, cough, and difficulty in breathing
Hematopoietic – decrease in the formation of blood cells
Ataxia - inability to coordinate voluntary muscular
movements
BEIR V 1990 800 excess deaths per 100,000 persons at 10
rem (0.1 Sv)
4,000 Hiroshima survivors in excess of 50 rem dose had an
extra 300 incidences of cancer
( ~ 7500 excess deaths per 100,000 at 50 rem) (0.5 Sv)
( ~ 1500 excess deaths per 100,000 at 10 rem) (0.1 Sv)
Lymphocyte - white blood cells
Leukopenia - abnormally low white blood cell count
Purpura - purple discoloration of skin caused by blood
bleeding into the skin tissue
Pneumonia - inflammation of lung tissue, accompanied by
fever, chills, cough, and difficulty in breathing
Hematopoietic – decrease in the formation of blood cells
Ataxia - inability to coordinate voluntary muscular
movements
BEIR V 1990 800 excess deaths per 100,000 persons at 10
rem
4,000 Hiroshima survivors in excess of 50 rem dose had an
extra 300 incidences of cancer
( ~ 7500 excess deaths per 100,000 at 50 rem) (0.5 Sv)
( ~ 1500 excess deaths per 100,000 at 10 rem) (0.1 Sv)
Radioactive Sources
Radioactive Sources
M edical Sources
M edical Sources
RADIATION EXPOSURE FROM M EDICAL
DIAGNOSTIC IM AGING PROCEDURES
HEALTH PHYSICS SOCIETY FACT SHEET
Ionizing radiation is used daily in hospitals and clinics to
perform diagnostic im aging procedures. For the
purposes of this fact sheet, the word radiation refers to
ionizing radiation. The m ost com m only m entioned form s
of ionizing radiation are x rays and gam m a rays.
Procedures that use radiation are necessary for
accurate diagnosis of disease and injury. They provide
im portant inform ation about your health to your doctor
and help ensure that you receive appropriate care.
Physicians and technologists perform ing these
procedures are trained to use the m inim um am ount of
radiation necessary for the procedure. Benefits from the
m edical procedure greatly outweigh any potential sm all
risk of harm from the am ount of radiation used.
RADIATION EXPOSURE FROM M EDICAL
DIAGNOSTIC IM AGING PROCEDURES
HEALTH PHYSICS SOCIETY FACT SHEET
Ionizing radiation is used daily in hospitals and clinics to
perform diagnostic im aging procedures. For the
purposes of this fact sheet, the word radiation refers to
ionizing radiation. The m ost com m only m entioned form s
of ionizing radiation are x rays and gam m a rays.
Procedures that use radiation are necessary for
accurate diagnosis of disease and injury. They provide
im portant inform ation about your health to your doctor
and help ensure that you receive appropriate care.
Physicians and technologists perform ing these
procedures are trained to use the m inim um am ount of
radiation necessary for the procedure. Benefits from the
m edical procedure greatly outweigh any potential sm all
risk of harm from the am ount of radiation used.
W hich types of diagnostic imaging procedures use
radiation?
• In x-ray procedures, x rays pass through the body to
form pictures on film or on a com puter or television
m onitor, which are viewed by a radiologist. If you have
an x-ray test, it will be perform ed with a standard x-ray
13
W hich types of diagnostic imaging procedures use
radiation?
• In x-ray procedures, x rays pass through the body to
form pictures on film or on a com puter or television
m onitor, which are viewed by a radiologist. If you have
an x-ray test, it will be perform ed with a standard x-ray
13
Radioactive Sources
Radioactive Sources
M edical Sources
M edical Sources
RADIATION EXPOSURE FROM M EDICAL
DIAGNOSTIC IM AGING PROCEDURES
HEALTH PHYSICS SOCIETY FACT SHEET
Ionizing radiation is used daily in hospitals and clinics to
perform diagnostic im aging procedures. For the
purposes of this fact sheet, the word radiation refers to
ionizing radiation. The m ost com m only m entioned form s
of ionizing radiation are x rays and gam m a rays.
Procedures that use radiation are necessary for
accurate diagnosis of disease and injury. They provide
im portant inform ation about your health to your doctor
and help ensure that you receive appropriate care.
Physicians and technologists perform ing these
procedures are trained to use the m inim um am ount of
radiation necessary for the procedure. Benefits from the
m edical procedure greatly outweigh any potential sm all
risk of harm from the am ount of radiation used.
RADIATION EXPOSURE FROM M EDICAL
DIAGNOSTIC IM AGING PROCEDURES
HEALTH PHYSICS SOCIETY FACT SHEET
Ionizing radiation is used daily in hospitals and clinics to
perform diagnostic im aging procedures. For the
purposes of this fact sheet, the word radiation refers to
ionizing radiation. The m ost com m only m entioned form s
of ionizing radiation are x rays and gam m a rays.
Procedures that use radiation are necessary for
accurate diagnosis of disease and injury. They provide
im portant inform ation about your health to your doctor
and help ensure that you receive appropriate care.
Physicians and technologists perform ing these
procedures are trained to use the m inim um am ount of
radiation necessary for the procedure. Benefits from the
m edical procedure greatly outweigh any potential sm all
risk of harm from the am ount of radiation used.
W hich types of diagnostic imaging procedures use
radiation?
• In x-ray procedures, x rays pass through the body to
form pictures on film or on a com puter or television
m onitor, which are viewed by a radiologist. If you have
an x-ray test, it will be perform ed with a standard x-ray
13
W hich types of diagnostic imaging procedures use
radiation?
• In x-ray procedures, x rays pass through the body to
form pictures on film or on a com puter or television
m onitor, which are viewed by a radiologist. If you have
an x-ray test, it will be perform ed with a standard x-ray
13
m achine or with a m ore sophisticated x-ray m achine
called a CT or CAT scan m achine.
• In nuclear m edicine procedures, a very sm all am ount
of radioactive m aterial is inhaled, injected, or swallowed
by the patient. If you have a nuclear m edicine exam , a
special cam era will be used to detect energy given off
by the radioactive m aterial in your body and form a
picture of your organs and their function on a com puter
m onitor. A nuclear m edicine physician views these
pictures. The radioactive m aterial typically disappears
from your body within a few hours or days.
m achine or with a m ore sophisticated x-ray m achine
called a CT or CAT scan m achine.
• In nuclear m edicine procedures, a very sm all am ount
of radioactive m aterial is inhaled, injected, or swallowed
by the patient. If you have a nuclear m edicine exam , a
special cam era will be used to detect energy given off
by the radioactive m aterial in your body and form a
picture of your organs and their function on a com puter
m onitor. A nuclear m edicine physician views these
pictures. The radioactive m aterial typically disappears
from your body within a few hours or days.
Do magnetic resonance imaging (M RI) and
ultrasound use radiation?
MRI and ultrasound procedures do not use ionizing
radiation. If you have either of these types of studies,
you are not exposed to radiation.
Do magnetic resonance imaging (M RI) and
ultrasound use radiation?
MRI and ultrasound procedures do not use ionizing
radiation. If you have either of these types of studies,
you are not exposed to radiation.
Do benefits from medical examinations using
radiation outw eigh the risks from the radiation?
Your doctor will order an x-ray test for you when it is
needed for accurate diagnosis of your condition.
Benefits from the m edical procedure greatly outweigh
any potential sm all risk of harm from the am ount of
radiation used. There is no conclusive evidence of
radiation causing harm at the levels patients receive
from diagnostic x-ray exam s. Although high doses of
radiation are linked to an increased risk of cancer, the
14
Do benefits from medical examinations using
radiation outw eigh the risks from the radiation?
Your doctor will order an x-ray test for you when it is
needed for accurate diagnosis of your condition.
Benefits from the m edical procedure greatly outweigh
any potential sm all risk of harm from the am ount of
radiation used. There is no conclusive evidence of
radiation causing harm at the levels patients receive
from diagnostic x-ray exam s. Although high doses of
radiation are linked to an increased risk of cancer, the
14
m achine or with a m ore sophisticated x-ray m achine
called a CT or CAT scan m achine.
• In nuclear m edicine procedures, a very sm all am ount
of radioactive m aterial is inhaled, injected, or swallowed
by the patient. If you have a nuclear m edicine exam , a
special cam era will be used to detect energy given off
by the radioactive m aterial in your body and form a
picture of your organs and their function on a com puter
m onitor. A nuclear m edicine physician views these
pictures. The radioactive m aterial typically disappears
from your body within a few hours or days.
m achine or with a m ore sophisticated x-ray m achine
called a CT or CAT scan m achine.
• In nuclear m edicine procedures, a very sm all am ount
of radioactive m aterial is inhaled, injected, or swallowed
by the patient. If you have a nuclear m edicine exam , a
special cam era will be used to detect energy given off
by the radioactive m aterial in your body and form a
picture of your organs and their function on a com puter
m onitor. A nuclear m edicine physician views these
pictures. The radioactive m aterial typically disappears
from your body within a few hours or days.
Do magnetic resonance imaging (M RI) and
ultrasound use radiation?
MRI and ultrasound procedures do not use ionizing
radiation. If you have either of these types of studies,
you are not exposed to radiation.
Do magnetic resonance imaging (M RI) and
ultrasound use radiation?
MRI and ultrasound procedures do not use ionizing
radiation. If you have either of these types of studies,
you are not exposed to radiation.
Do benefits from medical examinations using
radiation outw eigh the risks from the radiation?
Your doctor will order an x-ray test for you when it is
needed for accurate diagnosis of your condition.
Benefits from the m edical procedure greatly outweigh
any potential sm all risk of harm from the am ount of
radiation used. There is no conclusive evidence of
radiation causing harm at the levels patients receive
from diagnostic x-ray exam s. Although high doses of
radiation are linked to an increased risk of cancer, the
14
Do benefits from medical examinations using
radiation outw eigh the risks from the radiation?
Your doctor will order an x-ray test for you when it is
needed for accurate diagnosis of your condition.
Benefits from the m edical procedure greatly outweigh
any potential sm all risk of harm from the am ount of
radiation used. There is no conclusive evidence of
radiation causing harm at the levels patients receive
from diagnostic x-ray exam s. Although high doses of
radiation are linked to an increased risk of cancer, the
14
effects of the low doses of radiation used in diagnostic
im aging are not known. No one is certain if any real
risks are involved. Many diagnostic exposures are
sim ilar to exposure that we receive from natural
background radiation found all around us. You will note
that a few of the diagnostic exposures are m uch higher
than background or that m ultiple exposures will give an
accum ulated exposure higher than background.
Nevertheless, benefits of diagnostic m edical exam s are
vital to good patient care.
effects of the low doses of radiation used in diagnostic
im aging are not known. No one is certain if any real
risks are involved. Many diagnostic exposures are
sim ilar to exposure that we receive from natural
background radiation found all around us. You will note
that a few of the diagnostic exposures are m uch higher
than background or that m ultiple exposures will give an
accum ulated exposure higher than background.
Nevertheless, benefits of diagnostic m edical exam s are
vital to good patient care.
W hat are typical doses from medical procedures
involving radiation?
Radiation dose can be estim ated for som e com m on
diagnostic x-ray and nuclear m edicine studies. It is
im portant to note that these are only typical values.
Radiation doses differ for each person because of
differences in x-ray m achines and their settings, the
am ount of radioactive m aterial given in a nuclear
m edicine procedure, and the patient’s m etabolism .
The tables below give dose estim ates for typical
diagnostic x-ray and nuclear m edicine exam s. For
com parison, in the United States we receive about 3.0
m Sv (300 m rem ) of exposure from natural background
radiation every year. The effective dose listed is a
com parable whole-body dose from the exam .
W hat are typical doses from medical procedures
involving radiation?
Radiation dose can be estim ated for som e com m on
diagnostic x-ray and nuclear m edicine studies. It is
im portant to note that these are only typical values.
Radiation doses differ for each person because of
differences in x-ray m achines and their settings, the
am ount of radioactive m aterial given in a nuclear
m edicine procedure, and the patient’s m etabolism .
The tables below give dose estim ates for typical
diagnostic x-ray and nuclear m edicine exam s. For
com parison, in the United States we receive about 3.0
m Sv (300 m rem ) of exposure from natural background
radiation every year. The effective dose listed is a
com parable whole-body dose from the exam .
15
15
effects of the low doses of radiation used in diagnostic
im aging are not known. No one is certain if any real
risks are involved. Many diagnostic exposures are
sim ilar to exposure that we receive from natural
background radiation found all around us. You will note
that a few of the diagnostic exposures are m uch higher
than background or that m ultiple exposures will give an
accum ulated exposure higher than background.
Nevertheless, benefits of diagnostic m edical exam s are
vital to good patient care.
effects of the low doses of radiation used in diagnostic
im aging are not known. No one is certain if any real
risks are involved. Many diagnostic exposures are
sim ilar to exposure that we receive from natural
background radiation found all around us. You will note
that a few of the diagnostic exposures are m uch higher
than background or that m ultiple exposures will give an
accum ulated exposure higher than background.
Nevertheless, benefits of diagnostic m edical exam s are
vital to good patient care.
W hat are typical doses from medical procedures
involving radiation?
Radiation dose can be estim ated for som e com m on
diagnostic x-ray and nuclear m edicine studies. It is
im portant to note that these are only typical values.
Radiation doses differ for each person because of
differences in x-ray m achines and their settings, the
am ount of radioactive m aterial given in a nuclear
m edicine procedure, and the patient’s m etabolism .
The tables below give dose estim ates for typical
diagnostic x-ray and nuclear m edicine exam s. For
com parison, in the United States we receive about 3.0
m Sv (300 m rem ) of exposure from natural background
radiation every year. The effective dose listed is a
com parable whole-body dose from the exam .
W hat are typical doses from medical procedures
involving radiation?
Radiation dose can be estim ated for som e com m on
diagnostic x-ray and nuclear m edicine studies. It is
im portant to note that these are only typical values.
Radiation doses differ for each person because of
differences in x-ray m achines and their settings, the
am ount of radioactive m aterial given in a nuclear
m edicine procedure, and the patient’s m etabolism .
The tables below give dose estim ates for typical
diagnostic x-ray and nuclear m edicine exam s. For
com parison, in the United States we receive about 3.0
m Sv (300 m rem ) of exposure from natural background
radiation every year. The effective dose listed is a
com parable whole-body dose from the exam .
15
15
Typical Effective Radiation Dose
from Diagnostic X Ray— Single Exposure
Exam
Effective Dose m Sv (m rem )
Chest (LAT)
0.04 (4)
Chest (AP)
0.02 (2)
Skull (AP)
0.03 (3)
Skull (Lat)
0.01 (1)
Pelvis (AP)
0.7 (70)
Thoracic Spine (AP)
0.4 (40)
Lum bar Spine (AP)
0.7 (70)
Mam m ogram (four views)
0.7 (70)
Dental (lateral)
0.02 (2)
Dental (panoram ic)
0.09 (9)
DEXA (whole body)
0.0004 (0.04)
Hip
0.8 (80)
Hand or Foot
0.005 (0.5)
Abdom en
1.2 (120)
Typical Effective Radiation Dose
from Diagnostic X Ray— Single Exposure
Exam
Effective Dose mSv (mrem)
Chest (LAT)
0.04 (4)
Chest (AP)
0.02 (2)
Skull (AP)
0.03 (3)
Skull (Lat)
0.01 (1)
Pelvis (AP)
0.7 (70)
Thoracic Spine (AP)
0.4 (40)
Lum bar Spine (AP)
0.7 (70)
Mam m ogram (four views)
0.7 (70)
Dental (lateral)
0.02 (2)
Dental (panoram ic)
0.09 (9)
DEXA (whole body)
0.0004 (0.04)
Hip
0.8 (80)
Hand or Foot
0.005 (0.5)
Abdom en
1.2 (120)
16
16
Typical Effective Radiation Dose
from Diagnostic X Ray— Single Exposure
Exam
Effective Dose m Sv (m rem )
Chest (LAT)
0.04 (4)
Chest (AP)
0.02 (2)
Skull (AP)
0.03 (3)
Skull (Lat)
0.01 (1)
Pelvis (AP)
0.7 (70)
Thoracic Spine (AP)
0.4 (40)
Lum bar Spine (AP)
0.7 (70)
Mam m ogram (four views)
0.7 (70)
Dental (lateral)
0.02 (2)
Dental (panoram ic)
0.09 (9)
DEXA (whole body)
0.0004 (0.04)
Hip
0.8 (80)
Hand or Foot
0.005 (0.5)
Abdom en
1.2 (120)
Typical Effective Radiation Dose
from Diagnostic X Ray— Single Exposure
Exam
Effective Dose mSv (mrem)
Chest (LAT)
0.04 (4)
Chest (AP)
0.02 (2)
Skull (AP)
0.03 (3)
Skull (Lat)
0.01 (1)
Pelvis (AP)
0.7 (70)
Thoracic Spine (AP)
0.4 (40)
Lum bar Spine (AP)
0.7 (70)
Mam m ogram (four views)
0.7 (70)
Dental (lateral)
0.02 (2)
Dental (panoram ic)
0.09 (9)
DEXA (whole body)
0.0004 (0.04)
Hip
0.8 (80)
Hand or Foot
0.005 (0.5)
Abdom en
1.2 (120)
16
16
The following table shows the dose a patient could
receive if undergoing an entire procedure. For
exam ple, a lum bar spine series usually consists of five
x-ray exam s. CT stands for com puted tom ography
and is som etim es called a CAT scan.
The following table shows the dose a patient could
receive if undergoing an entire procedure. For
exam ple, a lum bar spine series usually consists of five
x-ray exam s. CT stands for com puted tom ography
and is som etim es called a CAT scan.
Com plete Exams
Effective Dose m Sv (m rem )
Intravenous Pyelogram
(kidneys, 6 film s)
2.5 (250)
Barium Swallow
(24 im ages, 106 sec. fluoroscopy)
1.5 (150)
Barium Enem a
(10 im ages, 137 sec. fluoroscopy)
7.0 (700)
CT Head
2.0 (200)
CT Chest
8.0 (800)
CT Abdom en
10.0 (1,000)
CT Pelvis
10.0 (1,000)
Angioplasty (heart study)
7.5 (750) - 57.0 (5,700)
Coronary Angiogram
4.6 (460) - 15.8 (1,580)
Com plete Exam s
Effective Dose mSv (mrem)
Intravenous Pyelogram
(kidneys, 6 film s)
2.5 (250)
Barium Swallow
(24 im ages, 106 sec. fluoroscopy)
1.5 (150)
Barium Enem a
(10 im ages, 137 sec. fluoroscopy)
7.0 (700)
CT Head
2.0 (200)
CT Chest
8.0 (800)
CT Abdom en
10.0 (1,000)
CT Pelvis
10.0 (1,000)
Angioplasty (heart study)
7.5 (750) - 57.0 (5,700)
Coronary Angiogram
4.6 (460) - 15.8 (1,580)
17
17
The following table shows the dose a patient could
receive if undergoing an entire procedure. For
exam ple, a lum bar spine series usually consists of five
x-ray exam s. CT stands for com puted tom ography
and is som etim es called a CAT scan.
The following table shows the dose a patient could
receive if undergoing an entire procedure. For
exam ple, a lum bar spine series usually consists of five
x-ray exam s. CT stands for com puted tom ography
and is som etim es called a CAT scan.
Com plete Exams
Effective Dose m Sv (m rem )
Intravenous Pyelogram
(kidneys, 6 film s)
2.5 (250)
Barium Swallow
(24 im ages, 106 sec. fluoroscopy)
1.5 (150)
Barium Enem a
(10 im ages, 137 sec. fluoroscopy)
7.0 (700)
CT Head
2.0 (200)
CT Chest
8.0 (800)
CT Abdom en
10.0 (1,000)
CT Pelvis
10.0 (1,000)
Angioplasty (heart study)
7.5 (750) - 57.0 (5,700)
Coronary Angiogram
4.6 (460) - 15.8 (1,580)
Com plete Exam s
Effective Dose mSv (mrem)
Intravenous Pyelogram
(kidneys, 6 film s)
2.5 (250)
Barium Swallow
(24 im ages, 106 sec. fluoroscopy)
1.5 (150)
Barium Enem a
(10 im ages, 137 sec. fluoroscopy)
7.0 (700)
CT Head
2.0 (200)
CT Chest
8.0 (800)
CT Abdom en
10.0 (1,000)
CT Pelvis
10.0 (1,000)
Angioplasty (heart study)
7.5 (750) - 57.0 (5,700)
Coronary Angiogram
4.6 (460) - 15.8 (1,580)
17
17
Typical Effective Radiation Dose
from Nuclear Medicine Examinations
Nuclear
RadioEffective Dose
Medicine
pharmaceutical
mSv (mrem)
Scan
15
Brain (PET)
O water
1.0 (100)
99m
Brain (perfusion)
Tc HMPAO
6.9 (690)
Hepatobiliary
99m
(liver flow)
Tc Sulfur Colloid
2.8 (280)
99m
Bone
Tc MDP
4.2 (420)
Lung Perfusion/
99m
133
Ventilation
Tc MAA & Xe
2.0 (200)
Kidney
99m
(filtration rate)
Tc DTPA
3.6 (360)
Kidney
99m
(tubular function)
Tc MAG3
5.2 (520)
67
Tumor/Infection
Ga
18.5 (1,850)
99m
Heart (rest)
Tc Cardiolite
6.7 (670)
99m
Heart (stress)
Tc Cardiolite
5.85 (585)
201
Heart
Tl chloride
11.8 (1,180)
99m
Heart (rest)
Tc Myoview
5.6 (560)
99m
Heart (stress)
Tc Myoview
5.6 (560)
18
Various PET Studies
F FDG
14.0 (1,400)
Typical Effective Radiation Dose
from Nuclear Medicine Examinations
Nuclear
RadioEffective Dose
Medicine
pharmaceutical
mSv (mrem)
Scan
15
Brain (PET)
O water
1.0 (100)
99m
Brain (perfusion)
Tc HMPAO
6.9 (690)
Hepatobiliary
99m
(liver flow)
Tc Sulfur Colloid
2.8 (280)
99m
Bone
Tc MDP
4.2 (420)
Lung Perfusion/
99m
133
Ventilation
Tc MAA & Xe
2.0 (200)
Kidney
99m
(filtration rate)
Tc DTPA
3.6 (360)
Kidney
99m
(tubular function)
Tc MAG3
5.2 (520)
67
Tumor/Infection
Ga
18.5 (1,850)
99m
Heart (rest)
Tc Cardiolite
6.7 (670)
99m
Heart (stress)
Tc Cardiolite
5.85 (585)
201
Heart
Tl chloride
11.8 (1,180)
99m
Heart (rest)
Tc Myoview
5.6 (560)
99m
Heart (stress)
Tc Myoview
5.6 (560)
18
Various PET Studies
F FDG
14.0 (1,400)
Commonly used radio-isotopes for PET scans
Half-life
Typical Tracer
Carbon-11
20 minutes
Methionine
Nitrogen-13
10 minutes
Ammonia
Oxygen-15
2 minutes
Water
Fluorine-18
110 minutes
Fluoro-deoxyglucose
Commonly used radio-isotopes for PET scans
Half-life
Typical Tracer
Carbon-11
20 minutes
Methionine
Nitrogen-13
10 minutes
Ammonia
Oxygen-15
2 minutes
Water
Fluorine-18
110 minutes
Fluoro-deoxyglucose
18
18
Typical Effective Radiation Dose
from Nuclear Medicine Examinations
Nuclear
RadioEffective Dose
Medicine
pharmaceutical
mSv (mrem)
Scan
15
Brain (PET)
O water
1.0 (100)
99m
Brain (perfusion)
Tc HMPAO
6.9 (690)
Hepatobiliary
99m
(liver flow)
Tc Sulfur Colloid
2.8 (280)
99m
Bone
Tc MDP
4.2 (420)
Lung Perfusion/
99m
133
Ventilation
Tc MAA & Xe
2.0 (200)
Kidney
99m
(filtration rate)
Tc DTPA
3.6 (360)
Kidney
99m
(tubular function)
Tc MAG3
5.2 (520)
67
Tumor/Infection
Ga
18.5 (1,850)
99m
Heart (rest)
Tc Cardiolite
6.7 (670)
99m
Heart (stress)
Tc Cardiolite
5.85 (585)
201
Heart
Tl chloride
11.8 (1,180)
99m
Heart (rest)
Tc Myoview
5.6 (560)
99m
Heart (stress)
Tc Myoview
5.6 (560)
18
Various PET Studies
F FDG
14.0 (1,400)
Typical Effective Radiation Dose
from Nuclear Medicine Examinations
Nuclear
RadioEffective Dose
Medicine
pharmaceutical
mSv (mrem)
Scan
15
Brain (PET)
O water
1.0 (100)
99m
Brain (perfusion)
Tc HMPAO
6.9 (690)
Hepatobiliary
99m
(liver flow)
Tc Sulfur Colloid
2.8 (280)
99m
Bone
Tc MDP
4.2 (420)
Lung Perfusion/
99m
133
Ventilation
Tc MAA & Xe
2.0 (200)
Kidney
99m
(filtration rate)
Tc DTPA
3.6 (360)
Kidney
99m
(tubular function)
Tc MAG3
5.2 (520)
67
Tumor/Infection
Ga
18.5 (1,850)
99m
Heart (rest)
Tc Cardiolite
6.7 (670)
99m
Heart (stress)
Tc Cardiolite
5.85 (585)
201
Heart
Tl chloride
11.8 (1,180)
99m
Heart (rest)
Tc Myoview
5.6 (560)
99m
Heart (stress)
Tc Myoview
5.6 (560)
18
Various PET Studies
F FDG
14.0 (1,400)
Commonly used radio-isotopes for PET scans
Half-life
Typical Tracer
Carbon-11
20 minutes
Methionine
Nitrogen-13
10 minutes
Ammonia
Oxygen-15
2 minutes
Water
Fluorine-18
110 minutes
Fluoro-deoxyglucose
Commonly used radio-isotopes for PET scans
Half-life
Typical Tracer
Carbon-11
20 minutes
Methionine
Nitrogen-13
10 minutes
Ammonia
Oxygen-15
2 minutes
Water
Fluorine-18
110 minutes
Fluoro-deoxyglucose
18
18
Isotopes used in Medicine
Isotopes used in Medicine
Many radioisotopes are made in nuclear reactors, some in
cyclotrons. Generally neutron-rich ones and those resulting
from nuclear fission need to be made in reactors, neutrondepleted ones are made in cyclotrons. There are about 40
activation product radioisotopes and five fission product ones
made in reactors. (from www.world-nuclear.org)
Many radioisotopes are made in nuclear reactors, some in
cyclotrons. Generally neutron-rich ones and those resulting
from nuclear fission need to be made in reactors, neutrondepleted ones are made in cyclotrons. There are about 40
activation product radioisotopes and five fission product ones
made in reactors. (from www.world-nuclear.org)
Reactor Radioisotopes (half-life indicated)
Bismuth-213 (46 min): Used for targeted alpha therapy
(TAT), especially cancers, as it has a high energy (8.4 MeV).
Chromium-51 (28 d): Used to label red blood cells and
quantify gastro-intestinal protein loss.
Cobalt-60 (5.27 yr): Formerly used for external beam
radiotherapy, now used more for sterilizing
Dysprosium-165 (2 h): Used as an aggregated hydroxide for
synovectomy treatment of arthritis.
Erbium-169 (9.4 d): Use for relieving arthritis pain in synovial
joints.
Holmium-166 (26 h): Being developed for diagnosis and
treatment of liver tumors.
Iodine-125 (60 d): Used in cancer brachytherapy (prostate
and brain), also diagnostically to evaluate the filtration rate of
kidneys and to diagnose deep vein thrombosis in the leg. It is
also widely used in radioimmuno-assays to show the
presence of hormones in tiny quantities.
Iodine-131 (8 d)*: Widely used in treating thyroid cancer and
in imaging the thyroid; also in diagnosis of abnormal liver
function, renal (kidney) blood flow and urinary tract
obstruction. A strong gamma emitter, but used for beta
therapy.
19
Reactor Radioisotopes (half-life indicated)
Bismuth-213 (46 min): Used for targeted alpha therapy
(TAT), especially cancers, as it has a high energy (8.4 MeV).
Chromium-51 (28 d): Used to label red blood cells and
quantify gastro-intestinal protein loss.
Cobalt-60 (5.27 yr): Formerly used for external beam
radiotherapy, now used more for sterilizing
Dysprosium-165 (2 h): Used as an aggregated hydroxide for
synovectomy treatment of arthritis.
Erbium-169 (9.4 d): Use for relieving arthritis pain in synovial
joints.
Holmium-166 (26 h): Being developed for diagnosis and
treatment of liver tumors.
Iodine-125 (60 d): Used in cancer brachytherapy (prostate
and brain), also diagnostically to evaluate the filtration rate of
kidneys and to diagnose deep vein thrombosis in the leg. It is
also widely used in radioimmuno-assays to show the
presence of hormones in tiny quantities.
Iodine-131 (8 d)*: Widely used in treating thyroid cancer and
in imaging the thyroid; also in diagnosis of abnormal liver
function, renal (kidney) blood flow and urinary tract
obstruction. A strong gamma emitter, but used for beta
therapy.
19
Isotopes used in Medicine
Isotopes used in Medicine
Many radioisotopes are made in nuclear reactors, some in
cyclotrons. Generally neutron-rich ones and those resulting
from nuclear fission need to be made in reactors, neutrondepleted ones are made in cyclotrons. There are about 40
activation product radioisotopes and five fission product ones
made in reactors. (from www.world-nuclear.org)
Many radioisotopes are made in nuclear reactors, some in
cyclotrons. Generally neutron-rich ones and those resulting
from nuclear fission need to be made in reactors, neutrondepleted ones are made in cyclotrons. There are about 40
activation product radioisotopes and five fission product ones
made in reactors. (from www.world-nuclear.org)
Reactor Radioisotopes (half-life indicated)
Bismuth-213 (46 min): Used for targeted alpha therapy
(TAT), especially cancers, as it has a high energy (8.4 MeV).
Chromium-51 (28 d): Used to label red blood cells and
quantify gastro-intestinal protein loss.
Cobalt-60 (5.27 yr): Formerly used for external beam
radiotherapy, now used more for sterilizing
Dysprosium-165 (2 h): Used as an aggregated hydroxide for
synovectomy treatment of arthritis.
Erbium-169 (9.4 d): Use for relieving arthritis pain in synovial
joints.
Holmium-166 (26 h): Being developed for diagnosis and
treatment of liver tumors.
Iodine-125 (60 d): Used in cancer brachytherapy (prostate
and brain), also diagnostically to evaluate the filtration rate of
kidneys and to diagnose deep vein thrombosis in the leg. It is
also widely used in radioimmuno-assays to show the
presence of hormones in tiny quantities.
Iodine-131 (8 d)*: Widely used in treating thyroid cancer and
in imaging the thyroid; also in diagnosis of abnormal liver
function, renal (kidney) blood flow and urinary tract
obstruction. A strong gamma emitter, but used for beta
therapy.
19
Reactor Radioisotopes (half-life indicated)
Bismuth-213 (46 min): Used for targeted alpha therapy
(TAT), especially cancers, as it has a high energy (8.4 MeV).
Chromium-51 (28 d): Used to label red blood cells and
quantify gastro-intestinal protein loss.
Cobalt-60 (5.27 yr): Formerly used for external beam
radiotherapy, now used more for sterilizing
Dysprosium-165 (2 h): Used as an aggregated hydroxide for
synovectomy treatment of arthritis.
Erbium-169 (9.4 d): Use for relieving arthritis pain in synovial
joints.
Holmium-166 (26 h): Being developed for diagnosis and
treatment of liver tumors.
Iodine-125 (60 d): Used in cancer brachytherapy (prostate
and brain), also diagnostically to evaluate the filtration rate of
kidneys and to diagnose deep vein thrombosis in the leg. It is
also widely used in radioimmuno-assays to show the
presence of hormones in tiny quantities.
Iodine-131 (8 d)*: Widely used in treating thyroid cancer and
in imaging the thyroid; also in diagnosis of abnormal liver
function, renal (kidney) blood flow and urinary tract
obstruction. A strong gamma emitter, but used for beta
therapy.
19
Iridium-192 (74 d): Supplied in wire form for use as an
internal radiotherapy source for cancer treatment (used then
removed).
Iron-59 (46 d): Used in studies of iron metabolism in the
spleen.
Lead-212 (10.6 h): Used in TAT for cancers, with decay
products Bi-212, Po-212, Tl-208.
Lutetium-177 (6.7 d): Lu-177 is increasingly important as it
emits just enough gamma for imaging while the beta radiation
does the therapy on small (e.g. endocrine) tumors. Its half-life
is long enough to allow sophisticated preparation for use. It is
usually produced by neutron activation of natural or enriched
lutetium-176 targets.
Molybdenum-99 (66 h)*: Used as the 'parent' in a generator
to produce technetium-99m.
Palladium-103 (17 d): Used to make brachytherapy
permanent implant seeds for early stage prostate cancer.
Phosphorus-32 (14 d): Used in the treatment of
polycythemia vera (excess red blood cells). Beta emitter.
Potassium-42 (12 h): Used for the determination of
exchangeable potassium in coronary blood flow.
Rhenium-186 (3.8 d): Used for pain relief in bone cancer.
Beta emitter with weak gamma for imaging.
Rhenium-188 (17 h): Used to beta irradiate coronary arteries
from an angioplasty balloon.
Samarium-153 (47 h): Sm-153 is very effective in relieving
the pain of secondary cancers lodged in the bone, sold as
Quadramet. Also very effective for prostate and breast
cancer.Beta emitter.
Selenium-75 (120 d): Used in the form of seleno-methionine
to study the production of digestive enzymes.
Sodium-24 (15 h): For studies of electrolytes within the body.
Iridium-192 (74 d): Supplied in wire form for use as an
internal radiotherapy source for cancer treatment (used then
removed).
Iron-59 (46 d): Used in studies of iron metabolism in the
spleen.
Lead-212 (10.6 h): Used in TAT for cancers, with decay
products Bi-212, Po-212, Tl-208.
Lutetium-177 (6.7 d): Lu-177 is increasingly important as it
emits just enough gamma for imaging while the beta radiation
does the therapy on small (e.g. endocrine) tumors. Its half-life
is long enough to allow sophisticated preparation for use. It is
usually produced by neutron activation of natural or enriched
lutetium-176 targets.
Molybdenum-99 (66 h)*: Used as the 'parent' in a generator
to produce technetium-99m.
Palladium-103 (17 d): Used to make brachytherapy
permanent implant seeds for early stage prostate cancer.
Phosphorus-32 (14 d): Used in the treatment of
polycythemia vera (excess red blood cells). Beta emitter.
Potassium-42 (12 h): Used for the determination of
exchangeable potassium in coronary blood flow.
Rhenium-186 (3.8 d): Used for pain relief in bone cancer.
Beta emitter with weak gamma for imaging.
Rhenium-188 (17 h): Used to beta irradiate coronary arteries
from an angioplasty balloon.
Samarium-153 (47 h): Sm-153 is very effective in relieving
the pain of secondary cancers lodged in the bone, sold as
Quadramet. Also very effective for prostate and breast
cancer.Beta emitter.
Selenium-75 (120 d): Used in the form of seleno-methionine
to study the production of digestive enzymes.
Sodium-24 (15 h): For studies of electrolytes within the body.
Iridium-192 (74 d): Supplied in wire form for use as an
internal radiotherapy source for cancer treatment (used then
removed).
Iron-59 (46 d): Used in studies of iron metabolism in the
spleen.
Lead-212 (10.6 h): Used in TAT for cancers, with decay
products Bi-212, Po-212, Tl-208.
Lutetium-177 (6.7 d): Lu-177 is increasingly important as it
emits just enough gamma for imaging while the beta radiation
does the therapy on small (e.g. endocrine) tumors. Its half-life
is long enough to allow sophisticated preparation for use. It is
usually produced by neutron activation of natural or enriched
lutetium-176 targets.
Molybdenum-99 (66 h)*: Used as the 'parent' in a generator
to produce technetium-99m.
Palladium-103 (17 d): Used to make brachytherapy
permanent implant seeds for early stage prostate cancer.
Phosphorus-32 (14 d): Used in the treatment of
polycythemia vera (excess red blood cells). Beta emitter.
Potassium-42 (12 h): Used for the determination of
exchangeable potassium in coronary blood flow.
Rhenium-186 (3.8 d): Used for pain relief in bone cancer.
Beta emitter with weak gamma for imaging.
Rhenium-188 (17 h): Used to beta irradiate coronary arteries
from an angioplasty balloon.
Samarium-153 (47 h): Sm-153 is very effective in relieving
the pain of secondary cancers lodged in the bone, sold as
Quadramet. Also very effective for prostate and breast
cancer.Beta emitter.
Selenium-75 (120 d): Used in the form of seleno-methionine
to study the production of digestive enzymes.
Sodium-24 (15 h): For studies of electrolytes within the body.
Iridium-192 (74 d): Supplied in wire form for use as an
internal radiotherapy source for cancer treatment (used then
removed).
Iron-59 (46 d): Used in studies of iron metabolism in the
spleen.
Lead-212 (10.6 h): Used in TAT for cancers, with decay
products Bi-212, Po-212, Tl-208.
Lutetium-177 (6.7 d): Lu-177 is increasingly important as it
emits just enough gamma for imaging while the beta radiation
does the therapy on small (e.g. endocrine) tumors. Its half-life
is long enough to allow sophisticated preparation for use. It is
usually produced by neutron activation of natural or enriched
lutetium-176 targets.
Molybdenum-99 (66 h)*: Used as the 'parent' in a generator
to produce technetium-99m.
Palladium-103 (17 d): Used to make brachytherapy
permanent implant seeds for early stage prostate cancer.
Phosphorus-32 (14 d): Used in the treatment of
polycythemia vera (excess red blood cells). Beta emitter.
Potassium-42 (12 h): Used for the determination of
exchangeable potassium in coronary blood flow.
Rhenium-186 (3.8 d): Used for pain relief in bone cancer.
Beta emitter with weak gamma for imaging.
Rhenium-188 (17 h): Used to beta irradiate coronary arteries
from an angioplasty balloon.
Samarium-153 (47 h): Sm-153 is very effective in relieving
the pain of secondary cancers lodged in the bone, sold as
Quadramet. Also very effective for prostate and breast
cancer.Beta emitter.
Selenium-75 (120 d): Used in the form of seleno-methionine
to study the production of digestive enzymes.
Sodium-24 (15 h): For studies of electrolytes within the body.
Strontium-89 (50 d)*: Very effective in reducing the pain of
prostate and bone cancer. Beta emitter.
Technetium-99m (6 h): Used in to image the skeleton and
heart muscle in particular, but also for brain, thyroid, lungs
(perfusion and ventilation), liver, spleen, kidney (structure and
filtration rate), gall bladder, bone marrow, salivary and
lacrimal glands, heart blood pool, infection and numerous
specialized medical studies. Produced from Mo-99 in a
generator.
Xenon-133 (5 d)*: Used for pulmonary (lung) ventilation
studies.
Ytterbium-169 (32 d): Used for cerebrospinal fluid studies in
the brain.
Ytterbium-177 (1.9 h): Progenitor of Lu-177.
Yttrium-90 (64 h)*: Used for cancer brachytherapy and as
silicate colloid for the relieving the pain of arthritis in larger
synovial joints. Pure beta emitter and of growing significance
in therapy.
Radioisotopes of cesium, gold and ruthenium are also used in
brachytherapy.
* fission product
Strontium-89 (50 d)*: Very effective in reducing the pain of
prostate and bone cancer. Beta emitter.
Technetium-99m (6 h): Used in to image the skeleton and
heart muscle in particular, but also for brain, thyroid, lungs
(perfusion and ventilation), liver, spleen, kidney (structure and
filtration rate), gall bladder, bone marrow, salivary and
lacrimal glands, heart blood pool, infection and numerous
specialized medical studies. Produced from Mo-99 in a
generator.
Xenon-133 (5 d)*: Used for pulmonary (lung) ventilation
studies.
Ytterbium-169 (32 d): Used for cerebrospinal fluid studies in
the brain.
Ytterbium-177 (1.9 h): Progenitor of Lu-177.
Yttrium-90 (64 h)*: Used for cancer brachytherapy and as
silicate colloid for the relieving the pain of arthritis in larger
synovial joints. Pure beta emitter and of growing significance
in therapy.
Radioisotopes of cesium, gold and ruthenium are also used in
brachytherapy.
* fission product
Cyclotron Radioisotopes
Carbon-11, Nitrogen-13, Oxygen-15, Fluorine-18: These are
positron emitters used in PET for studying brain physiology
and pathology, in particular for localising epileptic focus, and
in dementia, psychiatry and neuropharmacology studies.
They also have a significant role in cardiology. F-18 in FDG
(fluorodeoxyglucose) has become very important in detection
of cancers and the monitoring of progress in their treatment,
using PET.
21
Cyclotron Radioisotopes
Carbon-11, Nitrogen-13, Oxygen-15, Fluorine-18: These are
positron emitters used in PET for studying brain physiology
and pathology, in particular for localising epileptic focus, and
in dementia, psychiatry and neuropharmacology studies.
They also have a significant role in cardiology. F-18 in FDG
(fluorodeoxyglucose) has become very important in detection
of cancers and the monitoring of progress in their treatment,
using PET.
21
Strontium-89 (50 d)*: Very effective in reducing the pain of
prostate and bone cancer. Beta emitter.
Technetium-99m (6 h): Used in to image the skeleton and
heart muscle in particular, but also for brain, thyroid, lungs
(perfusion and ventilation), liver, spleen, kidney (structure and
filtration rate), gall bladder, bone marrow, salivary and
lacrimal glands, heart blood pool, infection and numerous
specialized medical studies. Produced from Mo-99 in a
generator.
Xenon-133 (5 d)*: Used for pulmonary (lung) ventilation
studies.
Ytterbium-169 (32 d): Used for cerebrospinal fluid studies in
the brain.
Ytterbium-177 (1.9 h): Progenitor of Lu-177.
Yttrium-90 (64 h)*: Used for cancer brachytherapy and as
silicate colloid for the relieving the pain of arthritis in larger
synovial joints. Pure beta emitter and of growing significance
in therapy.
Radioisotopes of cesium, gold and ruthenium are also used in
brachytherapy.
* fission product
Strontium-89 (50 d)*: Very effective in reducing the pain of
prostate and bone cancer. Beta emitter.
Technetium-99m (6 h): Used in to image the skeleton and
heart muscle in particular, but also for brain, thyroid, lungs
(perfusion and ventilation), liver, spleen, kidney (structure and
filtration rate), gall bladder, bone marrow, salivary and
lacrimal glands, heart blood pool, infection and numerous
specialized medical studies. Produced from Mo-99 in a
generator.
Xenon-133 (5 d)*: Used for pulmonary (lung) ventilation
studies.
Ytterbium-169 (32 d): Used for cerebrospinal fluid studies in
the brain.
Ytterbium-177 (1.9 h): Progenitor of Lu-177.
Yttrium-90 (64 h)*: Used for cancer brachytherapy and as
silicate colloid for the relieving the pain of arthritis in larger
synovial joints. Pure beta emitter and of growing significance
in therapy.
Radioisotopes of cesium, gold and ruthenium are also used in
brachytherapy.
* fission product
Cyclotron Radioisotopes
Carbon-11, Nitrogen-13, Oxygen-15, Fluorine-18: These are
positron emitters used in PET for studying brain physiology
and pathology, in particular for localising epileptic focus, and
in dementia, psychiatry and neuropharmacology studies.
They also have a significant role in cardiology. F-18 in FDG
(fluorodeoxyglucose) has become very important in detection
of cancers and the monitoring of progress in their treatment,
using PET.
21
Cyclotron Radioisotopes
Carbon-11, Nitrogen-13, Oxygen-15, Fluorine-18: These are
positron emitters used in PET for studying brain physiology
and pathology, in particular for localising epileptic focus, and
in dementia, psychiatry and neuropharmacology studies.
They also have a significant role in cardiology. F-18 in FDG
(fluorodeoxyglucose) has become very important in detection
of cancers and the monitoring of progress in their treatment,
using PET.
21
Cobalt-57 (272 d): Used as a marker to estimate organ size
and for in-vitro diagnostic kits.
Copper-64 (13 h): Used to study genetic diseases affecting
copper metabolism, such as Wilson's and Menke's diseases,
and for PET imaging of tumors, and therapy.
Copper-67 (2.6 d): Beta emitter, used in therapy.
Fluorine-18 as FLT (fluorothymidine), F-miso
(fluoromisonidazole), 18F-choline: tracer.
Gallium-67 (78 h): Used for tumor imaging and localization of
inflammatory lesions (infections).
Gallium-68 (68 min): Positron emitter used in PET and PETCT units. Derived from germanium-68 in a generator.
Germanium-68 (271 d): Used as the 'parent' in a generator to
produce Ga-68.
Indium-111 (2.8 d): Used for specialist diagnostic studies, eg
brain studies, infection and colon transit studies.
Iodine-123 (13 h): Increasingly used for diagnosis of thyroid
function, it is a gamma emitter without the beta radiation of I131.
Iodine-124: tracer.
Krypton-81m (13 sec) from Rubidium-81 (4.6 h): Kr-81m gas
can yield functional images of pulmonary ventilation, e.g. in
asthmatic patients, and for the early diagnosis of lung
diseases and function.
Rubidium-82 (1.26 min): Convenient PET agent in
myocardial perfusion imaging.
Strontium-82 (25 d): Used as the 'parent' in a generator to
produce Rb-82.
Thallium-201 (73 h): Used for diagnosis of coronary artery
disease other heart conditions such as heart muscle death
and for location of low-grade lymphomas.
22
Cobalt-57 (272 d): Used as a marker to estimate organ size
and for in-vitro diagnostic kits.
Copper-64 (13 h): Used to study genetic diseases affecting
copper metabolism, such as Wilson's and Menke's diseases,
and for PET imaging of tumors, and therapy.
Copper-67 (2.6 d): Beta emitter, used in therapy.
Fluorine-18 as FLT (fluorothymidine), F-miso
(fluoromisonidazole), 18F-choline: tracer.
Gallium-67 (78 h): Used for tumor imaging and localization of
inflammatory lesions (infections).
Gallium-68 (68 min): Positron emitter used in PET and PETCT units. Derived from germanium-68 in a generator.
Germanium-68 (271 d): Used as the 'parent' in a generator to
produce Ga-68.
Indium-111 (2.8 d): Used for specialist diagnostic studies, eg
brain studies, infection and colon transit studies.
Iodine-123 (13 h): Increasingly used for diagnosis of thyroid
function, it is a gamma emitter without the beta radiation of I131.
Iodine-124: tracer.
Krypton-81m (13 sec) from Rubidium-81 (4.6 h): Kr-81m gas
can yield functional images of pulmonary ventilation, e.g. in
asthmatic patients, and for the early diagnosis of lung
diseases and function.
Rubidium-82 (1.26 min): Convenient PET agent in
myocardial perfusion imaging.
Strontium-82 (25 d): Used as the 'parent' in a generator to
produce Rb-82.
Thallium-201 (73 h): Used for diagnosis of coronary artery
disease other heart conditions such as heart muscle death
and for location of low-grade lymphomas.
22
Cobalt-57 (272 d): Used as a marker to estimate organ size
and for in-vitro diagnostic kits.
Copper-64 (13 h): Used to study genetic diseases affecting
copper metabolism, such as Wilson's and Menke's diseases,
and for PET imaging of tumors, and therapy.
Copper-67 (2.6 d): Beta emitter, used in therapy.
Fluorine-18 as FLT (fluorothymidine), F-miso
(fluoromisonidazole), 18F-choline: tracer.
Gallium-67 (78 h): Used for tumor imaging and localization of
inflammatory lesions (infections).
Gallium-68 (68 min): Positron emitter used in PET and PETCT units. Derived from germanium-68 in a generator.
Germanium-68 (271 d): Used as the 'parent' in a generator to
produce Ga-68.
Indium-111 (2.8 d): Used for specialist diagnostic studies, eg
brain studies, infection and colon transit studies.
Iodine-123 (13 h): Increasingly used for diagnosis of thyroid
function, it is a gamma emitter without the beta radiation of I131.
Iodine-124: tracer.
Krypton-81m (13 sec) from Rubidium-81 (4.6 h): Kr-81m gas
can yield functional images of pulmonary ventilation, e.g. in
asthmatic patients, and for the early diagnosis of lung
diseases and function.
Rubidium-82 (1.26 min): Convenient PET agent in
myocardial perfusion imaging.
Strontium-82 (25 d): Used as the 'parent' in a generator to
produce Rb-82.
Thallium-201 (73 h): Used for diagnosis of coronary artery
disease other heart conditions such as heart muscle death
and for location of low-grade lymphomas.
22
Cobalt-57 (272 d): Used as a marker to estimate organ size
and for in-vitro diagnostic kits.
Copper-64 (13 h): Used to study genetic diseases affecting
copper metabolism, such as Wilson's and Menke's diseases,
and for PET imaging of tumors, and therapy.
Copper-67 (2.6 d): Beta emitter, used in therapy.
Fluorine-18 as FLT (fluorothymidine), F-miso
(fluoromisonidazole), 18F-choline: tracer.
Gallium-67 (78 h): Used for tumor imaging and localization of
inflammatory lesions (infections).
Gallium-68 (68 min): Positron emitter used in PET and PETCT units. Derived from germanium-68 in a generator.
Germanium-68 (271 d): Used as the 'parent' in a generator to
produce Ga-68.
Indium-111 (2.8 d): Used for specialist diagnostic studies, eg
brain studies, infection and colon transit studies.
Iodine-123 (13 h): Increasingly used for diagnosis of thyroid
function, it is a gamma emitter without the beta radiation of I131.
Iodine-124: tracer.
Krypton-81m (13 sec) from Rubidium-81 (4.6 h): Kr-81m gas
can yield functional images of pulmonary ventilation, e.g. in
asthmatic patients, and for the early diagnosis of lung
diseases and function.
Rubidium-82 (1.26 min): Convenient PET agent in
myocardial perfusion imaging.
Strontium-82 (25 d): Used as the 'parent' in a generator to
produce Rb-82.
Thallium-201 (73 h): Used for diagnosis of coronary artery
disease other heart conditions such as heart muscle death
and for location of low-grade lymphomas.
22
How can I obtain an estimate of my radiation dose from
medical exams?
Ask your doctor to refer you to a medical health physicist,
diagnostic medical physicist, or your hospital’s radiation
safety officer for information on medical radiation exposure
and an estimate of exposure.
How can I obtain an estimate of my radiation dose from
medical exams?
Ask your doctor to refer you to a medical health physicist,
diagnostic medical physicist, or your hospital’s radiation
safety officer for information on medical radiation exposure
and an estimate of exposure.
Internet Resources
To read more about x-ray exams, go to
www.radiologyinfo.org
Internet Resources
To read more about x-ray exams, go to
www.radiologyinfo.org
To read more about pregnancy and x rays, go to
hps.org/publicinformation/radterms
www.doseinforadar.com/RADARDoseRiskCalc.html
To read more about pregnancy and x rays, go to
hps.org/publicinformation/radterms
www.doseinforadar.com/RADARDoseRiskCalc.html
How do radiation doses from medical procedures
compare with background radiation doses and
occupational radiation doses?
Natural background radiation doses in the US range from 200
to 300 mrem/year (2 to 3 mSv/year).
How do radiation doses from medical procedures
compare with background radiation doses and
occupational radiation doses?
Natural background radiation doses in the US range from 200
to 300 mrem/year (2 to 3 mSv/year).
Exceptionally high natural background as high as 26 rem/year
(0.26 Sv/year) occur at Ramsar in Iran, Guarapari in Brazil,
Kerala in India, the northern Flinders Ranges in Australia, and
Yangjiang in China.
Exceptionally high natural background as high as 26 rem/year
(0.26 Sv/year) occur at Ramsar in Iran, Guarapari in Brazil,
Kerala in India, the northern Flinders Ranges in Australia, and
Yangjiang in China.
Occupational radiation doses
airline flight crew
1,000 mrem/yr
nuclear power plant 700 mrem/yr
medical personnel
70 mrem/yr
DOE employees
44 mrem/yr
Occupational radiation doses
airline flight crew
1,000 mrem/yr
nuclear power plant 700 mrem/yr
medical personnel
70 mrem/yr
DOE employees
44 mrem/yr
(10 mSv/yr)
(7 m Sv/yr)
(0.7 mSv/yr)
(0.44 mSv/yr)
(10 mSv/yr)
(7 m Sv/yr)
(0.7 mSv/yr)
(0.44 mSv/yr)
How can I obtain an estimate of my radiation dose from
medical exams?
Ask your doctor to refer you to a medical health physicist,
diagnostic medical physicist, or your hospital’s radiation
safety officer for information on medical radiation exposure
and an estimate of exposure.
How can I obtain an estimate of my radiation dose from
medical exams?
Ask your doctor to refer you to a medical health physicist,
diagnostic medical physicist, or your hospital’s radiation
safety officer for information on medical radiation exposure
and an estimate of exposure.
Internet Resources
To read more about x-ray exams, go to
www.radiologyinfo.org
Internet Resources
To read more about x-ray exams, go to
www.radiologyinfo.org
To read more about pregnancy and x rays, go to
hps.org/publicinformation/radterms
www.doseinforadar.com/RADARDoseRiskCalc.html
To read more about pregnancy and x rays, go to
hps.org/publicinformation/radterms
www.doseinforadar.com/RADARDoseRiskCalc.html
How do radiation doses from medical procedures
compare with background radiation doses and
occupational radiation doses?
Natural background radiation doses in the US range from 200
to 300 mrem/year (2 to 3 mSv/year).
How do radiation doses from medical procedures
compare with background radiation doses and
occupational radiation doses?
Natural background radiation doses in the US range from 200
to 300 mrem/year (2 to 3 mSv/year).
Exceptionally high natural background as high as 26 rem/year
(0.26 Sv/year) occur at Ramsar in Iran, Guarapari in Brazil,
Kerala in India, the northern Flinders Ranges in Australia, and
Yangjiang in China.
Exceptionally high natural background as high as 26 rem/year
(0.26 Sv/year) occur at Ramsar in Iran, Guarapari in Brazil,
Kerala in India, the northern Flinders Ranges in Australia, and
Yangjiang in China.
Occupational radiation doses
airline flight crew
1,000 mrem/yr
nuclear power plant 700 mrem/yr
medical personnel
70 mrem/yr
DOE employees
44 mrem/yr
Occupational radiation doses
airline flight crew
1,000 mrem/yr
nuclear power plant 700 mrem/yr
medical personnel
70 mrem/yr
DOE employees
44 mrem/yr
(10 mSv/yr)
(7 m Sv/yr)
(0.7 mSv/yr)
(0.44 mSv/yr)
(10 mSv/yr)
(7 m Sv/yr)
(0.7 mSv/yr)
(0.44 mSv/yr)
CONSUM ER PRODUCTS CONTAINING
RADIOACTIVE M ATERIALS
HEALTH PHYSICS SOCIETY FACT SHEET
Everything we encounter in our daily lives contains
som e radioactive m aterial, som e naturally occurring and
som e m anm ade: the air we breathe, the water we
drink, the food we eat, the ground we walk upon, and
the consum er products we purchase and use. Although
they m ight be fam iliar with the use of radiation to
diagnose disease and treat cancer, m any people, when
they hear the term s “radioactive” and “radiation,” tend to
think of m ushroom clouds and the m onster m utants that
inhabit the world of science fiction m ovies and com ic
books. Careful analyses can identify and quantify the
radioactive m aterial in just about anything.
CONSUM ER PRODUCTS CONTAINING
RADIOACTIVE M ATERIALS
HEALTH PHYSICS SOCIETY FACT SHEET
Everything we encounter in our daily lives contains
som e radioactive m aterial, som e naturally occurring and
som e m anm ade: the air we breathe, the water we
drink, the food we eat, the ground we walk upon, and
the consum er products we purchase and use. Although
they m ight be fam iliar with the use of radiation to
diagnose disease and treat cancer, m any people, when
they hear the term s “radioactive” and “radiation,” tend to
think of m ushroom clouds and the m onster m utants that
inhabit the world of science fiction m ovies and com ic
books. Careful analyses can identify and quantify the
radioactive m aterial in just about anything.
Smoke Detectors. Most residential sm oke detectors
contain a low-activity am ericium -241 source. Alpha
particles em itted by the am ericium ionize the air, m aking
the air conductive. Any sm oke particles that enter the
unit reduce the current and set off an alarm . Despite the
fact that these devices save lives, the question “are
sm oke detectors safe?” is still asked by those with an
inordinate fear of radiation. The answer, of course, is
“yes, they are safe.” Instructions for proper installation,
handling, and disposal of sm oke detectors are found on
the package. Smoke detectors have 0.9 uCi of Am-241.
Smoke Detectors. Most residential sm oke detectors
contain a low-activity am ericium -241 source. Alpha
particles em itted by the am ericium ionize the air, m aking
the air conductive. Any sm oke particles that enter the
unit reduce the current and set off an alarm . Despite the
fact that these devices save lives, the question “are
sm oke detectors safe?” is still asked by those with an
inordinate fear of radiation. The answer, of course, is
“yes, they are safe.” Instructions for proper installation,
handling, and disposal of sm oke detectors are found on
the package. Smoke detectors have 0.9 uCi of Am-241.
24
24
CONSUM ER PRODUCTS CONTAINING
RADIOACTIVE M ATERIALS
HEALTH PHYSICS SOCIETY FACT SHEET
Everything we encounter in our daily lives contains
som e radioactive m aterial, som e naturally occurring and
som e m anm ade: the air we breathe, the water we
drink, the food we eat, the ground we walk upon, and
the consum er products we purchase and use. Although
they m ight be fam iliar with the use of radiation to
diagnose disease and treat cancer, m any people, when
they hear the term s “radioactive” and “radiation,” tend to
think of m ushroom clouds and the m onster m utants that
inhabit the world of science fiction m ovies and com ic
books. Careful analyses can identify and quantify the
radioactive m aterial in just about anything.
CONSUM ER PRODUCTS CONTAINING
RADIOACTIVE M ATERIALS
HEALTH PHYSICS SOCIETY FACT SHEET
Everything we encounter in our daily lives contains
som e radioactive m aterial, som e naturally occurring and
som e m anm ade: the air we breathe, the water we
drink, the food we eat, the ground we walk upon, and
the consum er products we purchase and use. Although
they m ight be fam iliar with the use of radiation to
diagnose disease and treat cancer, m any people, when
they hear the term s “radioactive” and “radiation,” tend to
think of m ushroom clouds and the m onster m utants that
inhabit the world of science fiction m ovies and com ic
books. Careful analyses can identify and quantify the
radioactive m aterial in just about anything.
Smoke Detectors. Most residential sm oke detectors
contain a low-activity am ericium -241 source. Alpha
particles em itted by the am ericium ionize the air, m aking
the air conductive. Any sm oke particles that enter the
unit reduce the current and set off an alarm . Despite the
fact that these devices save lives, the question “are
sm oke detectors safe?” is still asked by those with an
inordinate fear of radiation. The answer, of course, is
“yes, they are safe.” Instructions for proper installation,
handling, and disposal of sm oke detectors are found on
the package. Smoke detectors have 0.9 uCi of Am-241.
Smoke Detectors. Most residential sm oke detectors
contain a low-activity am ericium -241 source. Alpha
particles em itted by the am ericium ionize the air, m aking
the air conductive. Any sm oke particles that enter the
unit reduce the current and set off an alarm . Despite the
fact that these devices save lives, the question “are
sm oke detectors safe?” is still asked by those with an
inordinate fear of radiation. The answer, of course, is
“yes, they are safe.” Instructions for proper installation,
handling, and disposal of sm oke detectors are found on
the package. Smoke detectors have 0.9 uCi of Am-241.
24
24
W atches and Clocks. Modern watches and clocks
som etim es use a sm all quantity of hydrogen-3 (tritium )
or prom ethium -147 as a source of light. Older (for
exam ple, pre-1970) watches and clocks used radium 226 as a source of light. If these older tim epieces are
opened and the dial or hands handled, som e of the
radium could be picked up and possibly ingested. As
such, caution should be exercised when handling these
item s.
W atches and Clocks. Modern watches and clocks
som etim es use a sm all quantity of hydrogen-3 (tritium )
or prom ethium -147 as a source of light. Older (for
exam ple, pre-1970) watches and clocks used radium 226 as a source of light. If these older tim epieces are
opened and the dial or hands handled, som e of the
radium could be picked up and possibly ingested. As
such, caution should be exercised when handling these
item s.
Ceramics. Ceram ic m aterials (for exam ple, tiles,
pottery) often contain elevated levels of naturally
occurring uranium , thorium , and/or potassium . In m any
cases, the activity is concentrated in the glaze. Unless
there is a large quantity of the m aterial, readings above
background are unlikely. Nevertheless, som e older (for
exam ple, pre-1960) tiles and pottery, especially those
with an orange-red glaze (for exam ple, Fiesta® ware)
can be quite radioactive.
Ceramics. Ceram ic m aterials (for exam ple, tiles,
pottery) often contain elevated levels of naturally
occurring uranium , thorium , and/or potassium . In m any
cases, the activity is concentrated in the glaze. Unless
there is a large quantity of the m aterial, readings above
background are unlikely. Nevertheless, som e older (for
exam ple, pre-1960) tiles and pottery, especially those
with an orange-red glaze (for exam ple, Fiesta® ware)
can be quite radioactive.
Glass. Glassware, especially antique glassware with a
yellow or greenish color, can contain easily detectable
quantities of uranium . Such uranium -containing glass is
often referred to as canary or vaseline glass. In part,
collectors like uranium glass for the attractive glow that
is produced when the glass is exposed to a black light.
Even ordinary glass can contain high-enough levels of
potassium -40 or thorium -232 to be detectable with a
25
Glass. Glassware, especially antique glassware with a
yellow or greenish color, can contain easily detectable
quantities of uranium . Such uranium -containing glass is
often referred to as canary or vaseline glass. In part,
collectors like uranium glass for the attractive glow that
is produced when the glass is exposed to a black light.
Even ordinary glass can contain high-enough levels of
potassium -40 or thorium -232 to be detectable with a
25
W atches and Clocks. Modern watches and clocks
som etim es use a sm all quantity of hydrogen-3 (tritium )
or prom ethium -147 as a source of light. Older (for
exam ple, pre-1970) watches and clocks used radium 226 as a source of light. If these older tim epieces are
opened and the dial or hands handled, som e of the
radium could be picked up and possibly ingested. As
such, caution should be exercised when handling these
item s.
W atches and Clocks. Modern watches and clocks
som etim es use a sm all quantity of hydrogen-3 (tritium )
or prom ethium -147 as a source of light. Older (for
exam ple, pre-1970) watches and clocks used radium 226 as a source of light. If these older tim epieces are
opened and the dial or hands handled, som e of the
radium could be picked up and possibly ingested. As
such, caution should be exercised when handling these
item s.
Ceramics. Ceram ic m aterials (for exam ple, tiles,
pottery) often contain elevated levels of naturally
occurring uranium , thorium , and/or potassium . In m any
cases, the activity is concentrated in the glaze. Unless
there is a large quantity of the m aterial, readings above
background are unlikely. Nevertheless, som e older (for
exam ple, pre-1960) tiles and pottery, especially those
with an orange-red glaze (for exam ple, Fiesta® ware)
can be quite radioactive.
Ceramics. Ceram ic m aterials (for exam ple, tiles,
pottery) often contain elevated levels of naturally
occurring uranium , thorium , and/or potassium . In m any
cases, the activity is concentrated in the glaze. Unless
there is a large quantity of the m aterial, readings above
background are unlikely. Nevertheless, som e older (for
exam ple, pre-1960) tiles and pottery, especially those
with an orange-red glaze (for exam ple, Fiesta® ware)
can be quite radioactive.
Glass. Glassware, especially antique glassware with a
yellow or greenish color, can contain easily detectable
quantities of uranium . Such uranium -containing glass is
often referred to as canary or vaseline glass. In part,
collectors like uranium glass for the attractive glow that
is produced when the glass is exposed to a black light.
Even ordinary glass can contain high-enough levels of
potassium -40 or thorium -232 to be detectable with a
25
Glass. Glassware, especially antique glassware with a
yellow or greenish color, can contain easily detectable
quantities of uranium . Such uranium -containing glass is
often referred to as canary or vaseline glass. In part,
collectors like uranium glass for the attractive glow that
is produced when the glass is exposed to a black light.
Even ordinary glass can contain high-enough levels of
potassium -40 or thorium -232 to be detectable with a
25
survey instrument. Older camera lenses (1950s-1970s)often
employed coatings of thorium-232 to alter the index of
refraction.
survey instrument. Older camera lenses (1950s-1970s)often
employed coatings of thorium-232 to alter the index of
refraction.
Fertilizer. Commercial fertilizers are designed to provide
varying levels of potassium, phosphorous, and nitrogen. Such
fertilizers can be measurably radioactive for two reasons:
potassium is naturally radioactive, and the phosphorous can
be derived from phosphate ore that contains elevated levels
of uranium. The abundance of radioactive K-40 in natural
potassium is 0.0118%. Phosphate ore leaches out and
concentrates any natural uranium ore it is in contact with.
Fertilizer. Commercial fertilizers are designed to provide
varying levels of potassium, phosphorous, and nitrogen. Such
fertilizers can be measurably radioactive for two reasons:
potassium is naturally radioactive, and the phosphorous can
be derived from phosphate ore that contains elevated levels
of uranium. The abundance of radioactive K-40 in natural
potassium is 0.0118%. Phosphate ore leaches out and
concentrates any natural uranium ore it is in contact with.
Food. Food contains a variety of different types and amounts
of naturally occurring radioactive materials. Although the
relatively small quantities of food in the home contain too little
radioactivity for the latter to be readily detectable, bulk
shipments of food have been known to set off the alarms of
radiation monitors at border crossings. One exception would
be low-sodium salt substitutes that contain enough
potassium-40 to be detectable with a radiation detector.
Food. Food contains a variety of different types and amounts
of naturally occurring radioactive materials. Although the
relatively small quantities of food in the home contain too little
radioactivity for the latter to be readily detectable, bulk
shipments of food have been known to set off the alarms of
radiation monitors at border crossings. One exception would
be low-sodium salt substitutes that contain enough
potassium-40 to be detectable with a radiation detector.
Water Softener. Water softeners often use potassium
instead of sodium to exchange the hardness in water with a
more soluble chemical. The natural potassium contains K-40.
Water Softener. Water softeners often use potassium
instead of sodium to exchange the hardness in water with a
more soluble chemical. The natural potassium contains K-40.
Tritium Exit Signs. Tritium exit signs typically contain 8
curies of tritium. The tritium is contained in vials along with a
chemical that gives off light in reaction to the beta radiation
emitted by the tritium. The bremsstrahlung radiation
produced by material reaction with the tritium beta can be
detected with a radiation detector.
Tritium Exit Signs. Tritium exit signs typically contain 8
curies of tritium. The tritium is contained in vials along with a
chemical that gives off light in reaction to the beta radiation
emitted by the tritium. The bremsstrahlung radiation
produced by material reaction with the tritium beta can be
detected with a radiation detector.
survey instrument. Older camera lenses (1950s-1970s)often
employed coatings of thorium-232 to alter the index of
refraction.
survey instrument. Older camera lenses (1950s-1970s)often
employed coatings of thorium-232 to alter the index of
refraction.
Fertilizer. Commercial fertilizers are designed to provide
varying levels of potassium, phosphorous, and nitrogen. Such
fertilizers can be measurably radioactive for two reasons:
potassium is naturally radioactive, and the phosphorous can
be derived from phosphate ore that contains elevated levels
of uranium. The abundance of radioactive K-40 in natural
potassium is 0.0118%. Phosphate ore leaches out and
concentrates any natural uranium ore it is in contact with.
Fertilizer. Commercial fertilizers are designed to provide
varying levels of potassium, phosphorous, and nitrogen. Such
fertilizers can be measurably radioactive for two reasons:
potassium is naturally radioactive, and the phosphorous can
be derived from phosphate ore that contains elevated levels
of uranium. The abundance of radioactive K-40 in natural
potassium is 0.0118%. Phosphate ore leaches out and
concentrates any natural uranium ore it is in contact with.
Food. Food contains a variety of different types and amounts
of naturally occurring radioactive materials. Although the
relatively small quantities of food in the home contain too little
radioactivity for the latter to be readily detectable, bulk
shipments of food have been known to set off the alarms of
radiation monitors at border crossings. One exception would
be low-sodium salt substitutes that contain enough
potassium-40 to be detectable with a radiation detector.
Food. Food contains a variety of different types and amounts
of naturally occurring radioactive materials. Although the
relatively small quantities of food in the home contain too little
radioactivity for the latter to be readily detectable, bulk
shipments of food have been known to set off the alarms of
radiation monitors at border crossings. One exception would
be low-sodium salt substitutes that contain enough
potassium-40 to be detectable with a radiation detector.
Water Softener. Water softeners often use potassium
instead of sodium to exchange the hardness in water with a
more soluble chemical. The natural potassium contains K-40.
Water Softener. Water softeners often use potassium
instead of sodium to exchange the hardness in water with a
more soluble chemical. The natural potassium contains K-40.
Tritium Exit Signs. Tritium exit signs typically contain 8
curies of tritium. The tritium is contained in vials along with a
chemical that gives off light in reaction to the beta radiation
emitted by the tritium. The bremsstrahlung radiation
produced by material reaction with the tritium beta can be
detected with a radiation detector.
Tritium Exit Signs. Tritium exit signs typically contain 8
curies of tritium. The tritium is contained in vials along with a
chemical that gives off light in reaction to the beta radiation
emitted by the tritium. The bremsstrahlung radiation
produced by material reaction with the tritium beta can be
detected with a radiation detector.
Gas Lantern M antles. W hile it is less com m on than it
once was, som e brands of gas lantern m antles
incorporate thorium -232. In fact it is the heating of the
thorium by the burning gas that is responsible for the
em ission of light. Such m antles are sufficiently
radioactive that they are often used as a check source
for radiation detectors.
Gas Lantern M antles. W hile it is less com m on than it
once was, som e brands of gas lantern m antles
incorporate thorium -232. In fact it is the heating of the
thorium by the burning gas that is responsible for the
em ission of light. Such m antles are sufficiently
radioactive that they are often used as a check source
for radiation detectors.
Antique Radioactive Curative Claims. In the past,
prim arily 1920 through 1950, a wide range of radioactive
products were sold as cure-alls, for exam ple, radium containing pills, pads, solutions, and devices designed
to add radon to drinking water. The states generally
have regulatory authority over these devices. In som e
cases, a state m ight even require that these devices be
registered or licensed. Most such devices are relatively
harm less but occasionally one can be encountered that
contains potentially hazardous levels of radium . If there
is any question about the safety of such devices, the
public is strongly encouraged to contact the state
radiation-control program for advice.
Antique Radioactive Curative Claims. In the past,
prim arily 1920 through 1950, a wide range of radioactive
products were sold as cure-alls, for exam ple, radium containing pills, pads, solutions, and devices designed
to add radon to drinking water. The states generally
have regulatory authority over these devices. In som e
cases, a state m ight even require that these devices be
registered or licensed. Most such devices are relatively
harm less but occasionally one can be encountered that
contains potentially hazardous levels of radium . If there
is any question about the safety of such devices, the
public is strongly encouraged to contact the state
radiation-control program for advice.
For further information contact the following:
National Council on Radiation Protection and
Measurem ents, “Radiation Exposure of the U.S.
Population from Consum er Products and Miscellaneous
Sources,” NCRP Report No. 95, Bethesda, MD, 1987.
U.S. Nuclear Regulatory Com m ission, “System atic
27
For further information contact the following:
National Council on Radiation Protection and
Measurem ents, “Radiation Exposure of the U.S.
Population from Consumer Products and Miscellaneous
Sources,” NCRP Report No. 95, Bethesda, MD, 1987.
U.S. Nuclear Regulatory Com m ission, “System atic
27
Gas Lantern M antles. W hile it is less com m on than it
once was, som e brands of gas lantern m antles
incorporate thorium -232. In fact it is the heating of the
thorium by the burning gas that is responsible for the
em ission of light. Such m antles are sufficiently
radioactive that they are often used as a check source
for radiation detectors.
Gas Lantern M antles. W hile it is less com m on than it
once was, som e brands of gas lantern m antles
incorporate thorium -232. In fact it is the heating of the
thorium by the burning gas that is responsible for the
em ission of light. Such m antles are sufficiently
radioactive that they are often used as a check source
for radiation detectors.
Antique Radioactive Curative Claims. In the past,
prim arily 1920 through 1950, a wide range of radioactive
products were sold as cure-alls, for exam ple, radium containing pills, pads, solutions, and devices designed
to add radon to drinking water. The states generally
have regulatory authority over these devices. In som e
cases, a state m ight even require that these devices be
registered or licensed. Most such devices are relatively
harm less but occasionally one can be encountered that
contains potentially hazardous levels of radium . If there
is any question about the safety of such devices, the
public is strongly encouraged to contact the state
radiation-control program for advice.
Antique Radioactive Curative Claims. In the past,
prim arily 1920 through 1950, a wide range of radioactive
products were sold as cure-alls, for exam ple, radium containing pills, pads, solutions, and devices designed
to add radon to drinking water. The states generally
have regulatory authority over these devices. In som e
cases, a state m ight even require that these devices be
registered or licensed. Most such devices are relatively
harm less but occasionally one can be encountered that
contains potentially hazardous levels of radium . If there
is any question about the safety of such devices, the
public is strongly encouraged to contact the state
radiation-control program for advice.
For further information contact the following:
National Council on Radiation Protection and
Measurem ents, “Radiation Exposure of the U.S.
Population from Consum er Products and Miscellaneous
Sources,” NCRP Report No. 95, Bethesda, MD, 1987.
U.S. Nuclear Regulatory Com m ission, “System atic
27
For further information contact the following:
National Council on Radiation Protection and
Measurem ents, “Radiation Exposure of the U.S.
Population from Consumer Products and Miscellaneous
Sources,” NCRP Report No. 95, Bethesda, MD, 1987.
U.S. Nuclear Regulatory Com m ission, “System atic
27
Radiological Assessm ent of Exem ptions for Source and
Byproduct Materials,” NUREG-1717, W ashington, DC,
2001. (This report is currently available at
http://www.nrc.gov/reading-rm /doccollections/nuregs/staff/.)
Radiological Assessm ent of Exem ptions for Source and
Byproduct Materials,” NUREG-1717, W ashington, DC,
2001. (This report is currently available at
http://www.nrc.gov/reading-rm /doccollections/nuregs/staff/.)
The Health Physics Society W eb site
(http://www.hps.org) contains a wealth of inform ation
about radiation and radioactivity, including an “Ask the
Experts” feature where specific questions about
radiation and radioactivity will be answered.
The Health Physics Society W eb site
(http://www.hps.org) contains a wealth of inform ation
about radiation and radioactivity, including an “Ask the
Experts” feature where specific questions about
radiation and radioactivity will be answered.
28
28
Radiological Assessm ent of Exem ptions for Source and
Byproduct Materials,” NUREG-1717, W ashington, DC,
2001. (This report is currently available at
http://www.nrc.gov/reading-rm /doccollections/nuregs/staff/.)
Radiological Assessm ent of Exem ptions for Source and
Byproduct Materials,” NUREG-1717, W ashington, DC,
2001. (This report is currently available at
http://www.nrc.gov/reading-rm /doccollections/nuregs/staff/.)
The Health Physics Society W eb site
(http://www.hps.org) contains a wealth of inform ation
about radiation and radioactivity, including an “Ask the
Experts” feature where specific questions about
radiation and radioactivity will be answered.
The Health Physics Society W eb site
(http://www.hps.org) contains a wealth of inform ation
about radiation and radioactivity, including an “Ask the
Experts” feature where specific questions about
radiation and radioactivity will be answered.
28
28
Industrial Radiation Sources
Industrial Radiation Sources
Manufacturing
Thickness of m etal, thickness of coatings, m oisture
content.
Ba-133, Co-60, Cs-134, Cs-137, Sb-124, Se-75, Sr-90,
Tm -170
Manufacturing
Thickness of m etal, thickness of coatings, m oisture
content.
Ba-133, Co-60, Cs-134, Cs-137, Sb-124, Se-75, Sr-90,
Tm -170
Chem ical Processing
Density, Thickness of coatings, Specific Gravity, Level
in process vessels
Gam m a em itters as above plus neutron sources
Am Be, PuBe, RaBe, Cf-252
Chem ical Processing
Density, Thickness of coatings, Specific Gravity, Level
in process vessels
Gam m a em itters as above plus neutron sources
Am Be, PuBe, RaBe, Cf-252
Construction
Moisture content, location of rebar
Gam m a em itters as above plus neutron sources as
above (moisture-density gauges)
Construction
Moisture content, location of rebar
Gam m a em itters as above plus neutron sources as
above (moisture-density gauges)
Mineral Processing
Percent of m inerals in process stream s
Gam m a em itters such as;
Am -241, Co-57, Cs-137
Mineral Processing
Percent of m inerals in process stream s
Gam m a em itters such as;
Am -241, Co-57, Cs-137
29
29
Industrial Radiation Sources
Industrial Radiation Sources
Manufacturing
Thickness of m etal, thickness of coatings, m oisture
content.
Ba-133, Co-60, Cs-134, Cs-137, Sb-124, Se-75, Sr-90,
Tm -170
Manufacturing
Thickness of m etal, thickness of coatings, m oisture
content.
Ba-133, Co-60, Cs-134, Cs-137, Sb-124, Se-75, Sr-90,
Tm -170
Chem ical Processing
Density, Thickness of coatings, Specific Gravity, Level
in process vessels
Gam m a em itters as above plus neutron sources
Am Be, PuBe, RaBe, Cf-252
Chem ical Processing
Density, Thickness of coatings, Specific Gravity, Level
in process vessels
Gam m a em itters as above plus neutron sources
Am Be, PuBe, RaBe, Cf-252
Construction
Moisture content, location of rebar
Gam m a em itters as above plus neutron sources as
above (moisture-density gauges)
Construction
Moisture content, location of rebar
Gam m a em itters as above plus neutron sources as
above (moisture-density gauges)
Mineral Processing
Percent of m inerals in process stream s
Gam m a em itters such as;
Am -241, Co-57, Cs-137
Mineral Processing
Percent of m inerals in process stream s
Gam m a em itters such as;
Am -241, Co-57, Cs-137
29
29
Coastal Engineering
Measurem ent of environm ental param eters, such as
levels of sedim ents in rivers and estuaries, and
m obilization of sedim ent.
Gam m a em itters such as;
Am -241, Co-60, Cs-137
Coastal Engineering
Measurem ent of environm ental param eters, such as
levels of sedim ents in rivers and estuaries, and
m obilization of sedim ent.
Gam m a em itters such as;
Am -241, Co-60, Cs-137
Non Destructive Exam ination
Radiography
Co-60, Cs-137, Ir-192
Non Destructive Exam ination
Radiography
Co-60, Cs-137, Ir-192
Oil Refining
Colum n scanning, level m easurem ent
Gam m a em itters as above
Am Be
Oil Refining
Colum n scanning, level m easurem ent
Gam m a em itters as above
Am Be
Coal Fired Boilers
Percent of ash in coal, m oisture content of coal
Gam m a sources such as;
Cs-137, Am -241
Coal Fired Boilers
Percent of ash in coal, m oisture content of coal
Gam m a sources such as;
Cs-137, Am -241
Drilling
Borehole logging (hydrogen content)
Co-60, Am Be
Drilling
Borehole logging (hydrogen content)
Co-60, Am Be
Agriculture
Percent soil m oisture
Am Be, PuBe, Cf-252
Agriculture
Percent soil m oisture
Am Be, PuBe, Cf-252
30
30
Coastal Engineering
Measurem ent of environm ental param eters, such as
levels of sedim ents in rivers and estuaries, and
m obilization of sedim ent.
Gam m a em itters such as;
Am -241, Co-60, Cs-137
Coastal Engineering
Measurem ent of environm ental param eters, such as
levels of sedim ents in rivers and estuaries, and
m obilization of sedim ent.
Gam m a em itters such as;
Am -241, Co-60, Cs-137
Non Destructive Exam ination
Radiography
Co-60, Cs-137, Ir-192
Non Destructive Exam ination
Radiography
Co-60, Cs-137, Ir-192
Oil Refining
Colum n scanning, level m easurem ent
Gam m a em itters as above
Am Be
Oil Refining
Colum n scanning, level m easurem ent
Gam m a em itters as above
Am Be
Coal Fired Boilers
Percent of ash in coal, m oisture content of coal
Gam m a sources such as;
Cs-137, Am -241
Coal Fired Boilers
Percent of ash in coal, m oisture content of coal
Gam m a sources such as;
Cs-137, Am -241
Drilling
Borehole logging (hydrogen content)
Co-60, Am Be
Drilling
Borehole logging (hydrogen content)
Co-60, Am Be
Agriculture
Percent soil m oisture
Am Be, PuBe, Cf-252
Agriculture
Percent soil m oisture
Am Be, PuBe, Cf-252
30
30
Hydrology
Soil m oisture
Am Be, PuBe, RaBe, Cf-252
Hydrology
Soil m oisture
Am Be, PuBe, RaBe, Cf-252
Medical Care
Sterilization of syringes, surgical instrum ents, surgery
consum ables, pharm aceuticals
Co-60
Medical Care
Sterilization of syringes, surgical instrum ents, surgery
consum ables, pharm aceuticals
Co-60
Materials Processing
Thickness or weight of m aterials, consistency, m oisture
content
Am -241, Pr-147, Kr-85, Sr-90
Materials Processing
Thickness or weight of m aterials, consistency, m oisture
content
Am -241, Pr-147, Kr-85, Sr-90
The gam m a and beta em itters listed range in activity
from below 1 curie to 1,000 curies. The neutron
sources range from less than 1 m illi-curie to 1 curie.
The range of gam m a or neutron exposures from these
sources is 0.05 rem /hr to 10,000 rem /hr (0.5 mSv/hr
to 100 Sv/hr) at 30 centim eters distance.
Refer to the section on gam m a ray constants for
gam m a exposure rates from these sources.
The gam m a and beta em itters listed range in activity
from below 1 curie to 1,000 curies. The neutron
sources range from less than 1 m illi-curie to 1 curie.
The range of gam m a or neutron exposures from these
sources is 0.05 rem /hr to 10,000 rem /hr (0.5 mSv/hr
to 100 Sv/hr at 30 centim eters distance.
Refer to the section on gam m a ray constants for
gam m a exposure rates from these sources.
Refer to the neutron section of this handbook
for neutron exposure rates.
Refer to the neutron section of this handbook
for neutron exposure rates.
31
31
Hydrology
Soil m oisture
Am Be, PuBe, RaBe, Cf-252
Hydrology
Soil m oisture
Am Be, PuBe, RaBe, Cf-252
Medical Care
Sterilization of syringes, surgical instrum ents, surgery
consum ables, pharm aceuticals
Co-60
Medical Care
Sterilization of syringes, surgical instrum ents, surgery
consum ables, pharm aceuticals
Co-60
Materials Processing
Thickness or weight of m aterials, consistency, m oisture
content
Am -241, Pr-147, Kr-85, Sr-90
Materials Processing
Thickness or weight of m aterials, consistency, m oisture
content
Am -241, Pr-147, Kr-85, Sr-90
The gam m a and beta em itters listed range in activity
from below 1 curie to 1,000 curies. The neutron
sources range from less than 1 m illi-curie to 1 curie.
The range of gam m a or neutron exposures from these
sources is 0.05 rem /hr to 10,000 rem /hr (0.5 mSv/hr
to 100 Sv/hr at 30 centim eters distance.
Refer to the section on gam m a ray constants for
gam m a exposure rates from these sources.
The gam m a and beta em itters listed range in activity
from below 1 curie to 1,000 curies. The neutron
sources range from less than 1 m illi-curie to 1 curie.
The range of gam m a or neutron exposures from these
sources is 0.05 rem /hr to 10,000 rem /hr (0.5 mSv/hr
to 100 Sv/hr at 30 centim eters distance.
Refer to the section on gam m a ray constants for
gam m a exposure rates from these sources.
Refer to the neutron section of this handbook
for neutron exposure rates.
Refer to the neutron section of this handbook
for neutron exposure rates.
31
31
Beta Dose Rates in rad/hr per mCi
Beta Dose Rates in rad/hr per mCi
MeV
1 cm
10 cm 30 cm 60 cm 90 cm 1.0 m
0.15
1,200
1.7
0
0
0
0
0.25
1,000
2.2
0.1
0
0
0
0.30
900
3.6
0.1
0
0
0
0.50
750
5.2
0.4
0.05
0.01
0
0.75
650
5.0
0.5
0.05
0.01
0
1.0
550
4.6
0.4
0.1
0
0
1.25
450
4.3
0.4
0.1
0.04
0.02
1.50
400
4.0
0.4
0.1
0.04
0.02
1.75
350
3.4
0.4
0.1
0.04
0.02
2.00
340
3.6
0.4
0.1
0.04
0.02
2.25
320
3.3
0.4
0.1
0.04
0.02
Beta dose should be treated as a “shallow” dose and should
not be summed with “deep” doses. This chart should also be
used to determine beta+ doses from positron emitters.
MeV
1 cm
10 cm 30 cm 60 cm 90 cm 1.0 m
0.15
1,200
1.7
0
0
0
0
0.25
1,000
2.2
0.1
0
0
0
0.30
900
3.6
0.1
0
0
0
0.50
750
5.2
0.4
0.05
0.01
0
0.75
650
5.0
0.5
0.05
0.01
0
1.0
550
4.6
0.4
0.1
0
0
1.25
450
4.3
0.4
0.1
0.04
0.02
1.50
400
4.0
0.4
0.1
0.04
0.02
1.75
350
3.4
0.4
0.1
0.04
0.02
2.00
340
3.6
0.4
0.1
0.04
0.02
2.25
320
3.3
0.4
0.1
0.04
0.02
Beta dose should be treated as a “shallow” dose and should
not be summed with “deep” doses. This chart should also be
used to determine beta+ doses from positron emitters.
Half-value Thickness vs Beta Energy
2
Isotope
Emax (MeV) Half-Value Thickness mg / cm
C-14
0.156
2
Tc-99
0.292
7.5
Cl-36
0.714
15
Sr/Y-90
0.546 / 2.284
150
U-238 Betas from short lived progeny
0.191 / 2.281
130
P-32
1.710
150
Estimate the half-value thickness for a beta emitter.
2
2
mg/cm = 50 x E
where E is Emax in MeV for the beta emitter
This equation tends to underestimate the half-value
thickness for low energy betas and overestimate the
half-value thickness for high energy betas.
Half-value Thickness vs Beta Energy
2
Isotope
Emax (MeV) Half-Value Thickness mg / cm
C-14
0.156
2
Tc-99
0.292
7.5
Cl-36
0.714
15
Sr/Y-90
0.546 / 2.284
150
U-238 Betas from short lived progeny
0.191 / 2.281
130
P-32
1.710
150
Estimate the half-value thickness for a beta emitter.
2
2
mg/cm = 50 x E
where E is Emax in MeV for the beta emitter
This equation tends to underestimate the half-value
thickness for low energy betas and overestimate the
half-value thickness for high energy betas.
Beta Dose Rates in rad/hr per mCi
Beta Dose Rates in rad/hr per mCi
MeV
1 cm
10 cm 30 cm 60 cm 90 cm 1.0 m
0.15
1,200
1.7
0
0
0
0
0.25
1,000
2.2
0.1
0
0
0
0.30
900
3.6
0.1
0
0
0
0.50
750
5.2
0.4
0.05
0.01
0
0.75
650
5.0
0.5
0.05
0.01
0
1.0
550
4.6
0.4
0.1
0
0
1.25
450
4.3
0.4
0.1
0.04
0.02
1.50
400
4.0
0.4
0.1
0.04
0.02
1.75
350
3.4
0.4
0.1
0.04
0.02
2.00
340
3.6
0.4
0.1
0.04
0.02
2.25
320
3.3
0.4
0.1
0.04
0.02
Beta dose should be treated as a “shallow” dose and should
not be summed with “deep” doses. This chart should also be
used to determine beta+ doses from positron emitters.
MeV
1 cm
10 cm 30 cm 60 cm 90 cm 1.0 m
0.15
1,200
1.7
0
0
0
0
0.25
1,000
2.2
0.1
0
0
0
0.30
900
3.6
0.1
0
0
0
0.50
750
5.2
0.4
0.05
0.01
0
0.75
650
5.0
0.5
0.05
0.01
0
1.0
550
4.6
0.4
0.1
0
0
1.25
450
4.3
0.4
0.1
0.04
0.02
1.50
400
4.0
0.4
0.1
0.04
0.02
1.75
350
3.4
0.4
0.1
0.04
0.02
2.00
340
3.6
0.4
0.1
0.04
0.02
2.25
320
3.3
0.4
0.1
0.04
0.02
Beta dose should be treated as a “shallow” dose and should
not be summed with “deep” doses. This chart should also be
used to determine beta+ doses from positron emitters.
Half-value Thickness vs Beta Energy
2
Isotope
Emax (MeV) Half-Value Thickness mg / cm
C-14
0.156
2
Tc-99
0.292
7.5
Cl-36
0.714
15
Sr/Y-90
0.546 / 2.284
150
U-238 Betas from short lived progeny
0.191 / 2.281
130
P-32
1.710
150
Estimate the half-value thickness for a beta emitter.
2
2
mg/cm = 50 x E
where E is Emax in MeV for the beta emitter
This equation tends to underestimate the half-value
thickness for low energy betas and overestimate the
half-value thickness for high energy betas.
Half-value Thickness vs Beta Energy
2
Isotope
Emax (MeV) Half-Value Thickness mg / cm
C-14
0.156
2
Tc-99
0.292
7.5
Cl-36
0.714
15
Sr/Y-90
0.546 / 2.284
150
U-238 Betas from short lived progeny
0.191 / 2.281
130
P-32
1.710
150
Estimate the half-value thickness for a beta emitter.
2
2
mg/cm = 50 x E
where E is Emax in MeV for the beta emitter
This equation tends to underestimate the half-value
thickness for low energy betas and overestimate the
half-value thickness for high energy betas.
Positron Emitters Beta+ Energy and % Abundance
C-11
N-13
O-15
F-18
Na-22
Al-26
V-48
Mn-52
Co-56
Ni-57
Co-58
Cu-62
Zn-65
Ga-68
As-74
Rb-82
Half-life
20.3 m
9.97 m
122 s
1.83 h
2.605 y
7.3E5 y
15.98 d
5.591 d
77.3 d
35.6 h
70.88 d
9.74 m
243.8 d
67.7 m
17.8 d
1.26 m
MeV (%)
0.960 (99.8%)
1.199 (99.8%)
1.732 (99.9%)
0.634 (96.7%)
0.546 (89.8%)
3.210 (100%)
0.697 (50.1%)
2.633 (94.9%)
1.458 (19.0%)
0.737 (7.0%), 0.865 (35.3%)
0.475 (14.9%)
2.926 (97.2%)
0.330 (1.4%)
0.822 (1.2%), 1.899 (89.1%)
0.945 (26.1%), 1.540 (3.0%)
2.601 (13.1%), 3.378 (81.8%)
Several of the positron emitters are useful in PET studies.
That usefulness is somewhat offset by the cost of producing
the radionuclides and the added complexity of radiation
protection. For all of the positron emitters the energy of the
Beta+ must be considered. Refer to the table of Beta Dose
Rates for estimates of beta+ radiation exposure. Also,
consider the annihilation photons when the positron comes
into contact with a beta-, annihilating their masses and
producing two 511 KeV photons. These photons present an
external radiation hazard. For the patient undergoing a PET
scan the combination of the positron energy and the photon
energy must be considered.
33
Positron Emitters Beta+ Energy and % Abundance
C-11
N-13
O-15
F-18
Na-22
Al-26
V-48
Mn-52
Co-56
Ni-57
Co-58
Cu-62
Zn-65
Ga-68
As-74
Rb-82
Half-life
20.3 m
9.97 m
122 s
1.83 h
2.605 y
7.3E5 y
15.98 d
5.591 d
77.3 d
35.6 h
70.88 d
9.74 m
243.8 d
67.7 m
17.8 d
1.26 m
MeV (%)
0.960 (99.8%)
1.199 (99.8%)
1.732 (99.9%)
0.634 (96.7%)
0.546 (89.8%)
3.210 (100%)
0.697 (50.1%)
2.633 (94.9%)
1.458 (19.0%)
0.737 (7.0%), 0.865 (35.3%)
0.475 (14.9%)
2.926 (97.2%)
0.330 (1.4%)
0.822 (1.2%), 1.899 (89.1%)
0.945 (26.1%), 1.540 (3.0%)
2.601 (13.1%), 3.378 (81.8%)
Several of the positron emitters are useful in PET studies.
That usefulness is somewhat offset by the cost of producing
the radionuclides and the added complexity of radiation
protection. For all of the positron emitters the energy of the
Beta+ must be considered. Refer to the table of Beta Dose
Rates for estimates of beta+ radiation exposure. Also,
consider the annihilation photons when the positron comes
into contact with a beta-, annihilating their masses and
producing two 511 KeV photons. These photons present an
external radiation hazard. For the patient undergoing a PET
scan the combination of the positron energy and the photon
energy must be considered.
33
Positron Emitters Beta+ Energy and % Abundance
C-11
N-13
O-15
F-18
Na-22
Al-26
V-48
Mn-52
Co-56
Ni-57
Co-58
Cu-62
Zn-65
Ga-68
As-74
Rb-82
Half-life
20.3 m
9.97 m
122 s
1.83 h
2.605 y
7.3E5 y
15.98 d
5.591 d
77.3 d
35.6 h
70.88 d
9.74 m
243.8 d
67.7 m
17.8 d
1.26 m
MeV (%)
0.960 (99.8%)
1.199 (99.8%)
1.732 (99.9%)
0.634 (96.7%)
0.546 (89.8%)
3.210 (100%)
0.697 (50.1%)
2.633 (94.9%)
1.458 (19.0%)
0.737 (7.0%), 0.865 (35.3%)
0.475 (14.9%)
2.926 (97.2%)
0.330 (1.4%)
0.822 (1.2%), 1.899 (89.1%)
0.945 (26.1%), 1.540 (3.0%)
2.601 (13.1%), 3.378 (81.8%)
Several of the positron emitters are useful in PET studies.
That usefulness is somewhat offset by the cost of producing
the radionuclides and the added complexity of radiation
protection. For all of the positron emitters the energy of the
Beta+ must be considered. Refer to the table of Beta Dose
Rates for estimates of beta+ radiation exposure. Also,
consider the annihilation photons when the positron comes
into contact with a beta-, annihilating their masses and
producing two 511 KeV photons. These photons present an
external radiation hazard. For the patient undergoing a PET
scan the combination of the positron energy and the photon
energy must be considered.
33
Positron Emitters Beta+ Energy and % Abundance
C-11
N-13
O-15
F-18
Na-22
Al-26
V-48
Mn-52
Co-56
Ni-57
Co-58
Cu-62
Zn-65
Ga-68
As-74
Rb-82
Half-life
20.3 m
9.97 m
122 s
1.83 h
2.605 y
7.3E5 y
15.98 d
5.591 d
77.3 d
35.6 h
70.88 d
9.74 m
243.8 d
67.7 m
17.8 d
1.26 m
MeV (%)
0.960 (99.8%)
1.199 (99.8%)
1.732 (99.9%)
0.634 (96.7%)
0.546 (89.8%)
3.210 (100%)
0.697 (50.1%)
2.633 (94.9%)
1.458 (19.0%)
0.737 (7.0%), 0.865 (35.3%)
0.475 (14.9%)
2.926 (97.2%)
0.330 (1.4%)
0.822 (1.2%), 1.899 (89.1%)
0.945 (26.1%), 1.540 (3.0%)
2.601 (13.1%), 3.378 (81.8%)
Several of the positron emitters are useful in PET studies.
That usefulness is somewhat offset by the cost of producing
the radionuclides and the added complexity of radiation
protection. For all of the positron emitters the energy of the
Beta+ must be considered. Refer to the table of Beta Dose
Rates for estimates of beta+ radiation exposure. Also,
consider the annihilation photons when the positron comes
into contact with a beta-, annihilating their masses and
producing two 511 KeV photons. These photons present an
external radiation hazard. For the patient undergoing a PET
scan the combination of the positron energy and the photon
energy must be considered.
33
Ci / g
= 3.578E5 / (T 1/2 in years x atom ic m ass)
GBq / g = 1.324E7 / (T 1/2 in years x atom ic m ass)
Rem /hr / Ci
Sv/hr / GBq
Half-Life
Ci/g
@ 30 cm GBq/g @ 30cm
227
Ac
21.77y
72.40
N/A
2.68E3
N/A
228
Ac
6.15h
2.24E6
2.82
8.29E7
7.62E-4
110
Ag
24.6s
4.17E9
0.18
1.54E11 4.79E-5
110m
Ag
249.79d
13.03
14.66 482
3.97E-3
111
Ag
7.45d
65.79
0.16
2.43E3
4.20E-5
26
Al
7.3E5y
0.019
16.6
0.699
4.49E-3
241
Am
432.7y
3.43
0.19
127
5.04E-5
242
Am
16.02h
8.08E5
0.23
2.99E7
6.25E-5
243
Am
7370y
0.20
0.23
7.40
6.22E-5
37
Ar
35.04d
1.01E5
N/A
3.73E6
N/A
39
Ar
269.0y
34.14
N/A
1.26E3
N/A
41
Ar
1.82h
4.20E7
7.73
1.55E9
2.09E-3
42
Ar
32.90y
259.20
N/A
9.59E3
N/A
74
As
17.8d
9.91E4
0.586 3.67E6
1.58E-4
215
At
0.100us
5.25E14 N/A
1.94E16 N/A
216
At
300us
1.74E14 N/A
6.44E15 N/A
218
At
1.6s
3.23E10 N/A
1.20E12 N/A
198
Au
2.695d
2.12E10 0.279 7.84E11 7.55E-5
131
Ba
11.5d
8.68E4
2.15
3.21E6
5.82E-4
133
Ba
10.52y
255.90
2.22
9.47E3
6.01E-4
137m
Ba
2.552m
5.37E8
4.44
1.99E10 1.20E-3
139
Ba
83.06m
1.63E7
0.173 6.03E8
4.68E-5
140
Ba
12.75d
7.32E4
0.871 2.71E6
2.36E-4
141
Ba
18.27m
7.31E7
2.4
2.70E9
6.50E-4
34
Ci / g
= 3.578E5 / (T 1/2 in years x atom ic m ass)
GBq / g = 1.324E7 / (T 1/2 in years x atom ic m ass)
Rem /hr / Ci
Sv/hr / GBq
Half-Life
Ci/g
@ 30 cm GBq/g @ 30cm
227
Ac
21.77y
72.40
N/A
2.68E3
N/A
228
Ac
6.15h
2.24E6
2.82
8.29E7
7.62E-4
110
Ag
24.6s
4.17E9
0.18
1.54E11 4.79E-5
110m
Ag
249.79d
13.03
14.66 482
3.97E-3
111
Ag
7.45d
65.79
0.16
2.43E3
4.20E-5
26
Al
7.3E5y
0.019
16.6
0.699
4.49E-3
241
Am
432.7y
3.43
0.19
127
5.04E-5
242
Am
16.02h
8.08E5
0.23
2.99E7
6.25E-5
243
Am
7370y
0.20
0.23
7.40
6.22E-5
37
Ar
35.04d
1.01E5
N/A
3.73E6
N/A
39
Ar
269.0y
34.14
N/A
1.26E3
N/A
41
Ar
1.82h
4.20E7
7.73
1.55E9
2.09E-3
42
Ar
32.90y
259.20
N/A
9.59E3
N/A
74
As
17.8d
9.91E4
0.586 3.67E6
1.58E-4
215
At
0.100us
5.25E14 N/A
1.94E16 N/A
216
At
300us
1.74E14 N/A
6.44E15 N/A
218
At
1.6s
3.23E10 N/A
1.20E12 N/A
198
Au
2.695d
2.12E10 0.279 7.84E11 7.55E-5
131
Ba
11.5d
8.68E4
2.15
3.21E6
5.82E-4
133
Ba
10.52y
255.90
2.22
9.47E3
6.01E-4
137m
Ba
2.552m
5.37E8
4.44
1.99E10 1.20E-3
139
Ba
83.06m
1.63E7
0.173 6.03E8
4.68E-5
140
Ba
12.75d
7.32E4
0.871 2.71E6
2.36E-4
141
Ba
18.27m
7.31E7
2.4
2.70E9
6.50E-4
34
Ci / g
= 3.578E5 / (T 1/2 in years x atom ic m ass)
GBq / g = 1.324E7 / (T 1/2 in years x atom ic m ass)
Rem /hr / Ci
Sv/hr / GBq
Half-Life
Ci/g
@ 30 cm GBq/g @ 30cm
227
Ac
21.77y
72.40
N/A
2.68E3
N/A
228
Ac
6.15h
2.24E6
2.82
8.29E7
7.62E-4
110
Ag
24.6s
4.17E9
0.18
1.54E11 4.79E-5
110m
Ag
249.79d
13.03
14.66 482
3.97E-3
111
Ag
7.45d
65.79
0.16
2.43E3
4.20E-5
26
Al
7.3E5y
0.019
16.6
0.699
4.49E-3
241
Am
432.7y
3.43
0.19
127
5.04E-5
242
Am
16.02h
8.08E5
0.23
2.99E7
6.25E-5
243
Am
7370y
0.20
0.23
7.40
6.22E-5
37
Ar
35.04d
1.01E5
N/A
3.73E6
N/A
39
Ar
269.0y
34.14
N/A
1.26E3
N/A
41
Ar
1.82h
4.20E7
7.73
1.55E9
2.09E-3
42
Ar
32.90y
259.20
N/A
9.59E3
N/A
74
As
17.8d
9.91E4
0.586 3.67E6
1.58E-4
215
At
0.100us
5.25E14 N/A
1.94E16 N/A
216
At
300us
1.74E14 N/A
6.44E15 N/A
218
At
1.6s
3.23E10 N/A
1.20E12 N/A
198
Au
2.695d
2.12E10 0.279 7.84E11 7.55E-5
131
Ba
11.5d
8.68E4
2.15
3.21E6
5.82E-4
133
Ba
10.52y
255.90
2.22
9.47E3
6.01E-4
137m
Ba
2.552m
5.37E8
4.44
1.99E10 1.20E-3
139
Ba
83.06m
1.63E7
0.173 6.03E8
4.68E-5
140
Ba
12.75d
7.32E4
0.871 2.71E6
2.36E-4
141
Ba
18.27m
7.31E7
2.4
2.70E9
6.50E-4
34
Ci / g
= 3.578E5 / (T 1/2 in years x atom ic m ass)
GBq / g = 1.324E7 / (T 1/2 in years x atom ic m ass)
Rem /hr / Ci
Sv/hr / GBq
Half-Life
Ci/g
@ 30 cm GBq/g @ 30cm
227
Ac
21.77y
72.40
N/A
2.68E3
N/A
228
Ac
6.15h
2.24E6
2.82
8.29E7
7.62E-4
110
Ag
24.6s
4.17E9
0.18
1.54E11 4.79E-5
110m
Ag
249.79d
13.03
14.66 482
3.97E-3
111
Ag
7.45d
65.79
0.16
2.43E3
4.20E-5
26
Al
7.3E5y
0.019
16.6
0.699
4.49E-3
241
Am
432.7y
3.43
0.19
127
5.04E-5
242
Am
16.02h
8.08E5
0.23
2.99E7
6.25E-5
243
Am
7370y
0.20
0.23
7.40
6.22E-5
37
Ar
35.04d
1.01E5
N/A
3.73E6
N/A
39
Ar
269.0y
34.14
N/A
1.26E3
N/A
41
Ar
1.82h
4.20E7
7.73
1.55E9
2.09E-3
42
Ar
32.90y
259.20
N/A
9.59E3
N/A
74
As
17.8d
9.91E4
0.586 3.67E6
1.58E-4
215
At
0.100us
5.25E14 N/A
1.94E16 N/A
216
At
300us
1.74E14 N/A
6.44E15 N/A
218
At
1.6s
3.23E10 N/A
1.20E12 N/A
198
Au
2.695d
2.12E10 0.279 7.84E11 7.55E-5
131
Ba
11.5d
8.68E4
2.15
3.21E6
5.82E-4
133
Ba
10.52y
255.90
2.22
9.47E3
6.01E-4
137m
Ba
2.552m
5.37E8
4.44
1.99E10 1.20E-3
139
Ba
83.06m
1.63E7
0.173 6.03E8
4.68E-5
140
Ba
12.75d
7.32E4
0.871 2.71E6
2.36E-4
141
Ba
18.27m
7.31E7
2.4
2.70E9
6.50E-4
34
142
Ba
7
Be
10
Be
210
Bi
210m
Bi
211
Bi
212
Bi
213
Bi
214
Bi
249
Bk
82
Br
84
Br
11
C
14
C
41
Ca
47
Ca
113
Cd
118
Cd
141
Ce
143
Ce
249
Cf
252
Cf
255
Cf
256
Cf
36
Cl
38
Cl
142
Ba
7
Be
10
Be
210
Bi
210m
Bi
211
Bi
212
Bi
213
Bi
214
Bi
249
Bk
82
Br
84
Br
11
C
14
C
41
Ca
47
Ca
113
Cd
118
Cd
141
Ce
143
Ce
249
Cf
252
Cf
255
Cf
256
Cf
36
Cl
38
Cl
Half-Life
10.6m
53.28d
1.51E6y
5.01d
3.04E6y
2.14m
60.6m
45.59m
19.9m
320d
17.68m
31.8m
1223s
5730y
1.03E5y
4.536d
7.70E15y
50.3m
32.5d
33.1h
351y
2.638y
85.0m
12.3m
3.01E5y
37.24m
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.25E8
1.01
4.63E9
2.73E-4
3.50E5
0.38
1.30E7
1.03E-4
0.024
N/A
0.875
N/A
1.24E5
N/A
4.59E6
N/A
5.61E-4 2.124 0.0207
5.75E-4
4.17E8
0.273 1.54E10 7.39E-5
1.47E7
N/A
5.44E8
N/A
1.94E7
0.739 7.17E8
2.00E-4
4.41E7
9.31
1.63E9
2.52E-3
1.64E3
N/A
6.07E4
N/A
1.33E8
2.15
4.92E9
5.82E-4
7.05E7
0.172 2.61E9
4.66E-5
8.38E8
6.815 3.10E10 1.84E-3
4.46
N/A
165
N/A
0.085
N/A
3.14
N/A
6.13E5
0.198 2.27E7
5.36E-5
4.12E-13 N/A
1.52E-11 N/A
3.17E7
N/A
1.17E9
N/A
2.85E4
0.422 1.06E6
1.14E-4
6.63E5
1.19
2.45E7
3.22E-4
4.09
1.98
151
5.35E-4
538
N/A
1.99E4
N/A
8.67E6
N/A
3.21E8
N/A
5.97E7
N/A
2.21E9
N/A
0.033
N/A
1.22
N/A
1.33E8
8.92
4.92E9
2.41E-3
35
Half-Life
10.6m
53.28d
1.51E6y
5.01d
3.04E6y
2.14m
60.6m
45.59m
19.9m
320d
17.68m
31.8m
1223s
5730y
1.03E5y
4.536d
7.70E15y
50.3m
32.5d
33.1h
351y
2.638y
85.0m
12.3m
3.01E5y
37.24m
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.25E8
1.01
4.63E9
2.73E-4
3.50E5
0.38
1.30E7
1.03E-4
0.024
N/A
0.875
N/A
1.24E5
N/A
4.59E6
N/A
5.61E-4 2.124 0.0207
5.75E-4
4.17E8
0.273 1.54E10 7.39E-5
1.47E7
N/A
5.44E8
N/A
1.94E7
0.739 7.17E8
2.00E-4
4.41E7
9.31
1.63E9
2.52E-3
1.64E3
N/A
6.07E4
N/A
1.33E8
2.15
4.92E9
5.82E-4
7.05E7
0.172 2.61E9
4.66E-5
8.38E8
6.815 3.10E10 1.84E-3
4.46
N/A
165
N/A
0.085
N/A
3.14
N/A
6.13E5
0.198 2.27E7
5.36E-5
4.12E-13 N/A
1.52E-11 N/A
3.17E7
N/A
1.17E9
N/A
2.85E4
0.422 1.06E6
1.14E-4
6.63E5
1.19
2.45E7
3.22E-4
4.09
1.98
151
5.35E-4
538
N/A
1.99E4
N/A
8.67E6
N/A
3.21E8
N/A
5.97E7
N/A
2.21E9
N/A
0.033
N/A
1.22
N/A
1.33E8
8.92
4.92E9
2.41E-3
35
142
Ba
7
Be
10
Be
210
Bi
210m
Bi
211
Bi
212
Bi
213
Bi
214
Bi
249
Bk
82
Br
84
Br
11
C
14
C
41
Ca
47
Ca
113
Cd
118
Cd
141
Ce
143
Ce
249
Cf
252
Cf
255
Cf
256
Cf
36
Cl
38
Cl
142
Ba
7
Be
10
Be
210
Bi
210m
Bi
211
Bi
212
Bi
213
Bi
214
Bi
249
Bk
82
Br
84
Br
11
C
14
C
41
Ca
47
Ca
113
Cd
118
Cd
141
Ce
143
Ce
249
Cf
252
Cf
255
Cf
256
Cf
36
Cl
38
Cl
Half-Life
10.6m
53.28d
1.51E6y
5.01d
3.04E6y
2.14m
60.6m
45.59m
19.9m
320d
17.68m
31.8m
1223s
5730y
1.03E5y
4.536d
7.70E15y
50.3m
32.5d
33.1h
351y
2.638y
85.0m
12.3m
3.01E5y
37.24m
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.25E8
1.01
4.63E9
2.73E-4
3.50E5
0.38
1.30E7
1.03E-4
0.024
N/A
0.875
N/A
1.24E5
N/A
4.59E6
N/A
5.61E-4 2.124 0.0207
5.75E-4
4.17E8
0.273 1.54E10 7.39E-5
1.47E7
N/A
5.44E8
N/A
1.94E7
0.739 7.17E8
2.00E-4
4.41E7
9.31
1.63E9
2.52E-3
1.64E3
N/A
6.07E4
N/A
1.33E8
2.15
4.92E9
5.82E-4
7.05E7
0.172 2.61E9
4.66E-5
8.38E8
6.815 3.10E10 1.84E-3
4.46
N/A
165
N/A
0.085
N/A
3.14
N/A
6.13E5
0.198 2.27E7
5.36E-5
4.12E-13 N/A
1.52E-11 N/A
3.17E7
N/A
1.17E9
N/A
2.85E4
0.422 1.06E6
1.14E-4
6.63E5
1.19
2.45E7
3.22E-4
4.09
1.98
151
5.35E-4
538
N/A
1.99E4
N/A
8.67E6
N/A
3.21E8
N/A
5.97E7
N/A
2.21E9
N/A
0.033
N/A
1.22
N/A
1.33E8
8.92
4.92E9
2.41E-3
35
Half-Life
10.6m
53.28d
1.51E6y
5.01d
3.04E6y
2.14m
60.6m
45.59m
19.9m
320d
17.68m
31.8m
1223s
5730y
1.03E5y
4.536d
7.70E15y
50.3m
32.5d
33.1h
351y
2.638y
85.0m
12.3m
3.01E5y
37.24m
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.25E8
1.01
4.63E9
2.73E-4
3.50E5
0.38
1.30E7
1.03E-4
0.024
N/A
0.875
N/A
1.24E5
N/A
4.59E6
N/A
5.61E-4 2.124 0.0207
5.75E-4
4.17E8
0.273 1.54E10 7.39E-5
1.47E7
N/A
5.44E8
N/A
1.94E7
0.739 7.17E8
2.00E-4
4.41E7
9.31
1.63E9
2.52E-3
1.64E3
N/A
6.07E4
N/A
1.33E8
2.15
4.92E9
5.82E-4
7.05E7
0.172 2.61E9
4.66E-5
8.38E8
6.815 3.10E10 1.84E-3
4.46
N/A
165
N/A
0.085
N/A
3.14
N/A
6.13E5
0.198 2.27E7
5.36E-5
4.12E-13 N/A
1.52E-11 N/A
3.17E7
N/A
1.17E9
N/A
2.85E4
0.422 1.06E6
1.14E-4
6.63E5
1.19
2.45E7
3.22E-4
4.09
1.98
151
5.35E-4
538
N/A
1.99E4
N/A
8.67E6
N/A
3.21E8
N/A
5.97E7
N/A
2.21E9
N/A
0.033
N/A
1.22
N/A
1.33E8
8.92
4.92E9
2.41E-3
35
Half-Life
242
Cm
162.8d
243
Cm
29.1y
244
Cm
18.1y
245
Cm
8500y
247
Cm
1.56E7y
56
Co
77.3d
57
Co
271.8d
58
Co
70.88d
60
Co
5.271y
51
Cr
27.70d
134
Cs
2.0648y
134m
Cs
2.903h
135
Cs
2.30E6y
136
Cs
13.16d
137
Cs
30.17y
138
Cs
33.41m
61
Cu
3.333h
62
Cu
9.74m
64
Cu
12.7h
154
Dy
3.00E6y
165
Dy
2.334h
253
Es
20.47d
256
Es
25.4m
152
Eu
13.537y
154
Eu
8.589y
155
Eu
4.7611y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
3.31E3
N/A
1.22E5
N/A
50.59
0.675 1.87E3
1.83E-4
81.0
N/A
3.00E3
N/A
0.17
0.325 6.36
8.80E-5
9.28E-5 1.87
3.43E-3 5.06E-4
3.02E4
21.36 1.12E6
5.77E-3
8.43E3
0.713 3.12E5
4.54E-4
3.18E4
6.81
1.18E6
1.84E-3
1.13E3
15.19 4.18E4
4.11E-3
9.24E4
0.207 3.42E6
5.61E-5
1.29E3
10.25 4.79E4
2.77E-3
8.06E6
0.0986 2.98E8
2.67E-5
1.15E-3 N/A
0.0427
N/A
7.30E4
6.85
2.70E6
1.85E-3
137m
86.6 See Ba
3.20E3
N/A
4.08E7
2.31
1.51E9
6.25E-4
1.54E7
1.05
5.71E8
2.84E-4
3.11E8
7.85
3.39E7
2.12E-3
3.86E6
1.228 1.43E8
3.33E-4
7.75E-4 N/A
0.0287
N/A
8.14E6
0.0918 3.01E8
2.49E-5
2.52E4
N/A
9.32E5
N/A
2.89E7
N/A
1.07E9
N/A
174.0
5.82
6.44E3
1.58E-3
270.6
7.06
1.00E4
1.91E-3
485.1
0.319 1.79E4
8.64E-5
36
Half-Life
242
Cm
162.8d
243
Cm
29.1y
244
Cm
18.1y
245
Cm
8500y
247
Cm
1.56E7y
56
Co
77.3d
57
Co
271.8d
58
Co
70.88d
60
Co
5.271y
51
Cr
27.70d
134
Cs
2.0648y
134m
Cs
2.903h
135
Cs
2.30E6y
136
Cs
13.16d
137
Cs
30.17y
138
Cs
33.41m
61
Cu
3.333h
62
Cu
9.74m
64
Cu
12.7h
154
Dy
3.00E6y
165
Dy
2.334h
253
Es
20.47d
256
Es
25.4m
152
Eu
13.537y
154
Eu
8.589y
155
Eu
4.7611y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
3.31E3
N/A
1.22E5
N/A
50.59
0.675 1.87E3
1.83E-4
81.0
N/A
3.00E3
N/A
0.17
0.325 6.36
8.80E-5
9.28E-5 1.87
3.43E-3 5.06E-4
3.02E4
21.36 1.12E6
5.77E-3
8.43E3
0.713 3.12E5
4.54E-4
3.18E4
6.81
1.18E6
1.84E-3
1.13E3
15.19 4.18E4
4.11E-3
9.24E4
0.207 3.42E6
5.61E-5
1.29E3
10.25 4.79E4
2.77E-3
8.06E6
0.0986 2.98E8
2.67E-5
1.15E-3 N/A
0.0427
N/A
7.30E4
6.85
2.70E6
1.85E-3
137m
86.6 See Ba
3.20E3
N/A
4.08E7
2.31
1.51E9
6.25E-4
1.54E7
1.05
5.71E8
2.84E-4
3.11E8
7.85
3.39E7
2.12E-3
3.86E6
1.228 1.43E8
3.33E-4
7.75E-4 N/A
0.0287
N/A
8.14E6
0.0918 3.01E8
2.49E-5
2.52E4
N/A
9.32E5
N/A
2.89E7
N/A
1.07E9
N/A
174.0
5.82
6.44E3
1.58E-3
270.6
7.06
1.00E4
1.91E-3
485.1
0.319 1.79E4
8.64E-5
36
Half-Life
242
Cm
162.8d
243
Cm
29.1y
244
Cm
18.1y
245
Cm
8500y
247
Cm
1.56E7y
56
Co
77.3d
57
Co
271.8d
58
Co
70.88d
60
Co
5.271y
51
Cr
27.70d
134
Cs
2.0648y
134m
Cs
2.903h
135
Cs
2.30E6y
136
Cs
13.16d
137
Cs
30.17y
138
Cs
33.41m
61
Cu
3.333h
62
Cu
9.74m
64
Cu
12.7h
154
Dy
3.00E6y
165
Dy
2.334h
253
Es
20.47d
256
Es
25.4m
152
Eu
13.537y
154
Eu
8.589y
155
Eu
4.7611y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
3.31E3
N/A
1.22E5
N/A
50.59
0.675 1.87E3
1.83E-4
81.0
N/A
3.00E3
N/A
0.17
0.325 6.36
8.80E-5
9.28E-5 1.87
3.43E-3 5.06E-4
3.02E4
21.36 1.12E6
5.77E-3
8.43E3
0.713 3.12E5
4.54E-4
3.18E4
6.81
1.18E6
1.84E-3
1.13E3
15.19 4.18E4
4.11E-3
9.24E4
0.207 3.42E6
5.61E-5
1.29E3
10.25 4.79E4
2.77E-3
8.06E6
0.0986 2.98E8
2.67E-5
1.15E-3 N/A
0.0427
N/A
7.30E4
6.85
2.70E6
1.85E-3
137m
86.6 See Ba
3.20E3
N/A
4.08E7
2.31
1.51E9
6.25E-4
1.54E7
1.05
5.71E8
2.84E-4
3.11E8
7.85
3.39E7
2.12E-3
3.86E6
1.228 1.43E8
3.33E-4
7.75E-4 N/A
0.0287
N/A
8.14E6
0.0918 3.01E8
2.49E-5
2.52E4
N/A
9.32E5
N/A
2.89E7
N/A
1.07E9
N/A
174.0
5.82
6.44E3
1.58E-3
270.6
7.06
1.00E4
1.91E-3
485.1
0.319 1.79E4
8.64E-5
36
Half-Life
242
Cm
162.8d
243
Cm
29.1y
244
Cm
18.1y
245
Cm
8500y
247
Cm
1.56E7y
56
Co
77.3d
57
Co
271.8d
58
Co
70.88d
60
Co
5.271y
51
Cr
27.70d
134
Cs
2.0648y
134m
Cs
2.903h
135
Cs
2.30E6y
136
Cs
13.16d
137
Cs
30.17y
138
Cs
33.41m
61
Cu
3.333h
62
Cu
9.74m
64
Cu
12.7h
154
Dy
3.00E6y
165
Dy
2.334h
253
Es
20.47d
256
Es
25.4m
152
Eu
13.537y
154
Eu
8.589y
155
Eu
4.7611y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
3.31E3
N/A
1.22E5
N/A
50.59
0.675 1.87E3
1.83E-4
81.0
N/A
3.00E3
N/A
0.17
0.325 6.36
8.80E-5
9.28E-5 1.87
3.43E-3 5.06E-4
3.02E4
21.36 1.12E6
5.77E-3
8.43E3
0.713 3.12E5
4.54E-4
3.18E4
6.81
1.18E6
1.84E-3
1.13E3
15.19 4.18E4
4.11E-3
9.24E4
0.207 3.42E6
5.61E-5
1.29E3
10.25 4.79E4
2.77E-3
8.06E6
0.0986 2.98E8
2.67E-5
1.15E-3 N/A
0.0427
N/A
7.30E4
6.85
2.70E6
1.85E-3
137m
86.6 See Ba
3.20E3
N/A
4.08E7
2.31
1.51E9
6.25E-4
1.54E7
1.05
5.71E8
2.84E-4
3.11E8
7.85
3.39E7
2.12E-3
3.86E6
1.228 1.43E8
3.33E-4
7.75E-4 N/A
0.0287
N/A
8.14E6
0.0918 3.01E8
2.49E-5
2.52E4
N/A
9.32E5
N/A
2.89E7
N/A
1.07E9
N/A
174.0
5.82
6.44E3
1.58E-3
270.6
7.06
1.00E4
1.91E-3
485.1
0.319 1.79E4
8.64E-5
36
Half-Life
156
Eu
15.19d
18
F
1.830h
55
Fe
2.73y
59
Fe
44.51d
60
Fe
1.50E6y
256
Fm
157.6m
219
Fr
20.0m s
221
Fr
4.9m
223
Fr
21.8m
67
Ga
3.2612d
148
Gd
75y
150
Gd
1.79E6y
152
Gd
1.08E14y
68
Ge
270.8d
3
H
12.3y
174
Hf
2.00E15y
203
Hg
46.612d
163
Ho
4.57E3y
166
Ho
26.8h
166m
Ho
1200y
123
I
13.27h
124
I
4.176d
125
I
60.1d
126
I
12.93d
129
I
1.57E7y
130
I
12.36h
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
5.51E4
1.3
2.04E6
3.52E-4
9.52E7
7.72
3.52E9
2.09E-3
2.38E3
N/A
8.81E4
N/A
4.97E4
7.34
1.84E6
1.98E-3
3.98E-3 N/A
0.147
N/A
4.66E6
N/A
1.72E8
N/A
2.58E12 N/A
9.53E13 N/A
1.74E8
0.163 6.43E9
4.41E-5
3.87E7
0.0952 1.43E9
2.58E-5
5.98E5
0.9381 2.21E7
2.54E-4
32.2
N/A
1.19E3
N/A
1.33E-3 N/A
0.0493
N/A
2.18E-11 N/A
8.07E-10 N/A
7.09E3
N/A
2.62E5
N/A
9.70E3
N/A
3.59E5
N/A
1.03E-12 N/A
3.81E-11 N/A
1.38E4
1.29
5.11E5
3.49E-4
0.48
N/A
17.8
N/A
7.05E5
0.1164 2.61E7
3.15E-5
1.80
5.39
66.5
1.46E-3
1.92E6
0.796 7.11E7
2.15E-4
2.52E5
5.53
9.34E6
1.50E-3
1.74E4
1.664 6.44E5
4.50E-4
7.97E4
4.34
2.95E6
1.17E-3
1.77E-4 0.736 6.55E-3 1.99E-4
1.55E6
4.76
5.74E7
1.29E-3
37
Half-Life
156
Eu
15.19d
18
F
1.830h
55
Fe
2.73y
59
Fe
44.51d
60
Fe
1.50E6y
256
Fm
157.6m
219
Fr
20.0m s
221
Fr
4.9m
223
Fr
21.8m
67
Ga
3.2612d
148
Gd
75y
150
Gd
1.79E6y
152
Gd
1.08E14y
68
Ge
270.8d
3
H
12.3y
174
Hf
2.00E15y
203
Hg
46.612d
163
Ho
4.57E3y
166
Ho
26.8h
166m
Ho
1200y
123
I
13.27h
124
I
4.176d
125
I
60.1d
126
I
12.93d
129
I
1.57E7y
130
I
12.36h
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
5.51E4
1.3
2.04E6
3.52E-4
9.52E7
7.72
3.52E9
2.09E-3
2.38E3
N/A
8.81E4
N/A
4.97E4
7.34
1.84E6
1.98E-3
3.98E-3 N/A
0.147
N/A
4.66E6
N/A
1.72E8
N/A
2.58E12 N/A
9.53E13 N/A
1.74E8
0.163 6.43E9
4.41E-5
3.87E7
0.0952 1.43E9
2.58E-5
5.98E5
0.9381 2.21E7
2.54E-4
32.2
N/A
1.19E3
N/A
1.33E-3 N/A
0.0493
N/A
2.18E-11 N/A
8.07E-10 N/A
7.09E3
N/A
2.62E5
N/A
9.70E3
N/A
3.59E5
N/A
1.03E-12 N/A
3.81E-11 N/A
1.38E4
1.29
5.11E5
3.49E-4
0.48
N/A
17.8
N/A
7.05E5
0.1164 2.61E7
3.15E-5
1.80
5.39
66.5
1.46E-3
1.92E6
0.796 7.11E7
2.15E-4
2.52E5
5.53
9.34E6
1.50E-3
1.74E4
1.664 6.44E5
4.50E-4
7.97E4
4.34
2.95E6
1.17E-3
1.77E-4 0.736 6.55E-3 1.99E-4
1.55E6
4.76
5.74E7
1.29E-3
37
Half-Life
156
Eu
15.19d
18
F
1.830h
55
Fe
2.73y
59
Fe
44.51d
60
Fe
1.50E6y
256
Fm
157.6m
219
Fr
20.0m s
221
Fr
4.9m
223
Fr
21.8m
67
Ga
3.2612d
148
Gd
75y
150
Gd
1.79E6y
152
Gd
1.08E14y
68
Ge
270.8d
3
H
12.3y
174
Hf
2.00E15y
203
Hg
46.612d
163
Ho
4.57E3y
166
Ho
26.8h
166m
Ho
1200y
123
I
13.27h
124
I
4.176d
125
I
60.1d
126
I
12.93d
129
I
1.57E7y
130
I
12.36h
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
5.51E4
1.3
2.04E6
3.52E-4
9.52E7
7.72
3.52E9
2.09E-3
2.38E3
N/A
8.81E4
N/A
4.97E4
7.34
1.84E6
1.98E-3
3.98E-3 N/A
0.147
N/A
4.66E6
N/A
1.72E8
N/A
2.58E12 N/A
9.53E13 N/A
1.74E8
0.163 6.43E9
4.41E-5
3.87E7
0.0952 1.43E9
2.58E-5
5.98E5
0.9381 2.21E7
2.54E-4
32.2
N/A
1.19E3
N/A
1.33E-3 N/A
0.0493
N/A
2.18E-11 N/A
8.07E-10 N/A
7.09E3
N/A
2.62E5
N/A
9.70E3
N/A
3.59E5
N/A
1.03E-12 N/A
3.81E-11 N/A
1.38E4
1.29
5.11E5
3.49E-4
0.48
N/A
17.8
N/A
7.05E5
0.1164 2.61E7
3.15E-5
1.80
5.39
66.5
1.46E-3
1.92E6
0.796 7.11E7
2.15E-4
2.52E5
5.53
9.34E6
1.50E-3
1.74E4
1.664 6.44E5
4.50E-4
7.97E4
4.34
2.95E6
1.17E-3
1.77E-4 0.736 6.55E-3 1.99E-4
1.55E6
4.76
5.74E7
1.29E-3
37
Half-Life
156
Eu
15.19d
18
F
1.830h
55
Fe
2.73y
59
Fe
44.51d
60
Fe
1.50E6y
256
Fm
157.6m
219
Fr
20.0m s
221
Fr
4.9m
223
Fr
21.8m
67
Ga
3.2612d
148
Gd
75y
150
Gd
1.79E6y
152
Gd
1.08E14y
68
Ge
270.8d
3
H
12.3y
174
Hf
2.00E15y
203
Hg
46.612d
163
Ho
4.57E3y
166
Ho
26.8h
166m
Ho
1200y
123
I
13.27h
124
I
4.176d
125
I
60.1d
126
I
12.93d
129
I
1.57E7y
130
I
12.36h
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
5.51E4
1.3
2.04E6
3.52E-4
9.52E7
7.72
3.52E9
2.09E-3
2.38E3
N/A
8.81E4
N/A
4.97E4
7.34
1.84E6
1.98E-3
3.98E-3 N/A
0.147
N/A
4.66E6
N/A
1.72E8
N/A
2.58E12 N/A
9.53E13 N/A
1.74E8
0.163 6.43E9
4.41E-5
3.87E7
0.0952 1.43E9
2.58E-5
5.98E5
0.9381 2.21E7
2.54E-4
32.2
N/A
1.19E3
N/A
1.33E-3 N/A
0.0493
N/A
2.18E-11 N/A
8.07E-10 N/A
7.09E3
N/A
2.62E5
N/A
9.70E3
N/A
3.59E5
N/A
1.03E-12 N/A
3.81E-11 N/A
1.38E4
1.29
5.11E5
3.49E-4
0.48
N/A
17.8
N/A
7.05E5
0.1164 2.61E7
3.15E-5
1.80
5.39
66.5
1.46E-3
1.92E6
0.796 7.11E7
2.15E-4
2.52E5
5.53
9.34E6
1.50E-3
1.74E4
1.664 6.44E5
4.50E-4
7.97E4
4.34
2.95E6
1.17E-3
1.77E-4 0.736 6.55E-3 1.99E-4
1.55E6
4.76
5.74E7
1.29E-3
37
131
I
132
I
133
I
134
I
135
I
111
In
113m
In
115
In
192
Ir
40
K
42
K
43
K
85
Kr
85m
Kr
87
Kr
88
Kr
89
Kr
140
La
142
La
177
Lu
52
Mn
52m
Mn
53
Mn
54
Mn
56
Mn
99
Mo
131
I
132
I
133
I
134
I
135
I
111
In
113m
In
115
In
192
Ir
40
K
42
K
43
K
85
Kr
85m
Kr
87
Kr
88
Kr
89
Kr
140
La
142
La
177
Lu
52
Mn
52m
Mn
53
Mn
54
Mn
56
Mn
99
Mo
Half-Life
8.040d
2.295h
20.8h
52.6m
6.57h
2.8047d
1.6582h
4.41E14y
73.83d
1.28E9y
12.36h
22.3h
10.73y
4.48h
76.3m
2.84h
3.15m
1.678d
91.1m
6.73d
5.591d
21.2m
3.74E6y
312.2d
2.578h
67h
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.24E5
3.14
4.59E6
8.49E-4
1.04E7
5.17
3.83E8
1.40E-3
1.13E6
4.54
4.18E7
1.23E-3
2.67E7
17.47 9.88E8
4.72E-3
3.53E6
9.57
1.31E8
2.59E-3
4.20E5
3.717 1.55E7
1.01E-3
1.69E7
1.53
6.25E8
4.14E-4
7.06E-12 N/A
2.61E-10 N/A
9.21E3
6.56
3.41E5
1.77E-3
6.99E-6 0.91
2.59E-4 2.46E-4
6.04E6
1.4
2.23E8
3.78E-4
3.27E6
5.6
1.21E8
1.51E-3
392.0
0.02
1.45E4
5.40E-6
8.24E6
0.96
3.05E8
2.60E-4
2.84E7
3.18
1.05E9
8.61E-4
1.26E7
8.9
4.64E8
2.41E-3
6.71E8
3.96
2.48E10 1.07E-3
5.56E5
13.61 2.06E7
3.68E-3
1.46E7
0.675 5.38E8
1.83E-4
1.10E5
0.170 4.06E6
4.61E-5
4.49E5
18.6
1.66E7
5.03E-3
1.72E8
1.48
6.35E9
4.01E-4
1.81E-3 N/A
0.0669
N/A
7.75E3
5.67
2.87E5
1.53E-3
2.17E7
10.24 8.03E8
2.77E-3
4.80E5
1.25
1.78E7
3.38E-4
38
Half-Life
8.040d
2.295h
20.8h
52.6m
6.57h
2.8047d
1.6582h
4.41E14y
73.83d
1.28E9y
12.36h
22.3h
10.73y
4.48h
76.3m
2.84h
3.15m
1.678d
91.1m
6.73d
5.591d
21.2m
3.74E6y
312.2d
2.578h
67h
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.24E5
3.14
4.59E6
8.49E-4
1.04E7
5.17
3.83E8
1.40E-3
1.13E6
4.54
4.18E7
1.23E-3
2.67E7
17.47 9.88E8
4.72E-3
3.53E6
9.57
1.31E8
2.59E-3
4.20E5
3.717 1.55E7
1.01E-3
1.69E7
1.53
6.25E8
4.14E-4
7.06E-12 N/A
2.61E-10 N/A
9.21E3
6.56
3.41E5
1.77E-3
6.99E-6 0.91
2.59E-4 2.46E-4
6.04E6
1.4
2.23E8
3.78E-4
3.27E6
5.6
1.21E8
1.51E-3
392.0
0.02
1.45E4
5.40E-6
8.24E6
0.96
3.05E8
2.60E-4
2.84E7
3.18
1.05E9
8.61E-4
1.26E7
8.9
4.64E8
2.41E-3
6.71E8
3.96
2.48E10 1.07E-3
5.56E5
13.61 2.06E7
3.68E-3
1.46E7
0.675 5.38E8
1.83E-4
1.10E5
0.170 4.06E6
4.61E-5
4.49E5
18.6
1.66E7
5.03E-3
1.72E8
1.48
6.35E9
4.01E-4
1.81E-3 N/A
0.0669
N/A
7.75E3
5.67
2.87E5
1.53E-3
2.17E7
10.24 8.03E8
2.77E-3
4.80E5
1.25
1.78E7
3.38E-4
38
131
I
132
I
133
I
134
I
135
I
111
In
113m
In
115
In
192
Ir
40
K
42
K
43
K
85
Kr
85m
Kr
87
Kr
88
Kr
89
Kr
140
La
142
La
177
Lu
52
Mn
52m
Mn
53
Mn
54
Mn
56
Mn
99
Mo
131
I
132
I
133
I
134
I
135
I
111
In
113m
In
115
In
192
Ir
40
K
42
K
43
K
85
Kr
85m
Kr
87
Kr
88
Kr
89
Kr
140
La
142
La
177
Lu
52
Mn
52m
Mn
53
Mn
54
Mn
56
Mn
99
Mo
Half-Life
8.040d
2.295h
20.8h
52.6m
6.57h
2.8047d
1.6582h
4.41E14y
73.83d
1.28E9y
12.36h
22.3h
10.73y
4.48h
76.3m
2.84h
3.15m
1.678d
91.1m
6.73d
5.591d
21.2m
3.74E6y
312.2d
2.578h
67h
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.24E5
3.14
4.59E6
8.49E-4
1.04E7
5.17
3.83E8
1.40E-3
1.13E6
4.54
4.18E7
1.23E-3
2.67E7
17.47 9.88E8
4.72E-3
3.53E6
9.57
1.31E8
2.59E-3
4.20E5
3.717 1.55E7
1.01E-3
1.69E7
1.53
6.25E8
4.14E-4
7.06E-12 N/A
2.61E-10 N/A
9.21E3
6.56
3.41E5
1.77E-3
6.99E-6 0.91
2.59E-4 2.46E-4
6.04E6
1.4
2.23E8
3.78E-4
3.27E6
5.6
1.21E8
1.51E-3
392.0
0.02
1.45E4
5.40E-6
8.24E6
0.96
3.05E8
2.60E-4
2.84E7
3.18
1.05E9
8.61E-4
1.26E7
8.9
4.64E8
2.41E-3
6.71E8
3.96
2.48E10 1.07E-3
5.56E5
13.61 2.06E7
3.68E-3
1.46E7
0.675 5.38E8
1.83E-4
1.10E5
0.170 4.06E6
4.61E-5
4.49E5
18.6
1.66E7
5.03E-3
1.72E8
1.48
6.35E9
4.01E-4
1.81E-3 N/A
0.0669
N/A
7.75E3
5.67
2.87E5
1.53E-3
2.17E7
10.24 8.03E8
2.77E-3
4.80E5
1.25
1.78E7
3.38E-4
38
Half-Life
8.040d
2.295h
20.8h
52.6m
6.57h
2.8047d
1.6582h
4.41E14y
73.83d
1.28E9y
12.36h
22.3h
10.73y
4.48h
76.3m
2.84h
3.15m
1.678d
91.1m
6.73d
5.591d
21.2m
3.74E6y
312.2d
2.578h
67h
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.24E5
3.14
4.59E6
8.49E-4
1.04E7
5.17
3.83E8
1.40E-3
1.13E6
4.54
4.18E7
1.23E-3
2.67E7
17.47 9.88E8
4.72E-3
3.53E6
9.57
1.31E8
2.59E-3
4.20E5
3.717 1.55E7
1.01E-3
1.69E7
1.53
6.25E8
4.14E-4
7.06E-12 N/A
2.61E-10 N/A
9.21E3
6.56
3.41E5
1.77E-3
6.99E-6 0.91
2.59E-4 2.46E-4
6.04E6
1.4
2.23E8
3.78E-4
3.27E6
5.6
1.21E8
1.51E-3
392.0
0.02
1.45E4
5.40E-6
8.24E6
0.96
3.05E8
2.60E-4
2.84E7
3.18
1.05E9
8.61E-4
1.26E7
8.9
4.64E8
2.41E-3
6.71E8
3.96
2.48E10 1.07E-3
5.56E5
13.61 2.06E7
3.68E-3
1.46E7
0.675 5.38E8
1.83E-4
1.10E5
0.170 4.06E6
4.61E-5
4.49E5
18.6
1.66E7
5.03E-3
1.72E8
1.48
6.35E9
4.01E-4
1.81E-3 N/A
0.0669
N/A
7.75E3
5.67
2.87E5
1.53E-3
2.17E7
10.24 8.03E8
2.77E-3
4.80E5
1.25
1.78E7
3.38E-4
38
Half-Life
13
N
9.965m
16
N
7.13s
22
Na
2.605y
24
Na
14.96h
94
Nb
2.03E5y
95
Nb
34.975d
144
Nd
2.29E15y
57
Ni
35.6h
59
Ni
7.60E4y
63
Ni
101y
65
Ni
2.52h
66
Ni
54.6h
237
Np
2.14E6y
238
Np
2.117d
239
Np
2.355d
240
Np
61.9m
15
O
122.2s
186
Os
2E15y
32
P
14.28d
33
P
25.34d
231
Pa
3.28E4y
233
Pa
26.967d
234
Pa
6.69h
234m
Pa
1.17m
209
Pb
3.253h
210
Pb
22.3y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.45E9
6.814 5.37E10 1.84E-3
9.89E10 16.57 3.66E12 4.48E-3
6.24E3
14.85 2.31E5
4.01E-3
8.73E6
20.55 3.23E8
5.55E-3
0.19
10.20 6.94
2.76E-3
3.93E4
4.74
1.46E6
1.28E-3
1.09E-12 N/A
4.02E-11 N/A
1.54E6
12
5.70E7
3.24E-3
0.080
12.5
2.95
3.38E-3
56.23
N/A
2.08E3
N/A
1.91E7
3.4
7.07E8
9.19E-4
8.71E5
N/A
3.22E7
N/A
7.05E-4 0.0868 0.0261
2.35E-5
2.59E5
0.018 9.59E6
4.87E-6
2.32E5
0.594 8.58E6
1.61E-4
1.27E7
0.863 4.68E8
2.34E-4
6.15E9
7.98
2.29E11 2.16E-3
9.62E-13 0.613 3.56E-11 1.66E-4
2.86E5
N/A
1.06E7
N/A
1.56E5
N/A
5.78E6
N/A
0.047
0.104 1.75
2.81E-5
2.08E4
1.27
7.69E5
3.44E-4
2.00E6
7.03
7.40E7
1.90E-3
6.86E8
0.05
2.54E10 1.35E-5
4.61E6
N/A
1.71E8
N/A
76.4
0.0203 2.83E3
5.50E-6
39
Half-Life
13
N
9.965m
16
N
7.13s
22
Na
2.605y
24
Na
14.96h
94
Nb
2.03E5y
95
Nb
34.975d
144
Nd
2.29E15y
57
Ni
35.6h
59
Ni
7.60E4y
63
Ni
101y
65
Ni
2.52h
66
Ni
54.6h
237
Np
2.14E6y
238
Np
2.117d
239
Np
2.355d
240
Np
61.9m
15
O
122.2s
186
Os
2E15y
32
P
14.28d
33
P
25.34d
231
Pa
3.28E4y
233
Pa
26.967d
234
Pa
6.69h
234m
Pa
1.17m
209
Pb
3.253h
210
Pb
22.3y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.45E9
6.814 5.37E10 1.84E-3
9.89E10 16.57 3.66E12 4.48E-3
6.24E3
14.85 2.31E5
4.01E-3
8.73E6
20.55 3.23E8
5.55E-3
0.19
10.20 6.94
2.76E-3
3.93E4
4.74
1.46E6
1.28E-3
1.09E-12 N/A
4.02E-11 N/A
1.54E6
12
5.70E7
3.24E-3
0.080
12.5
2.95
3.38E-3
56.23
N/A
2.08E3
N/A
1.91E7
3.4
7.07E8
9.19E-4
8.71E5
N/A
3.22E7
N/A
7.05E-4 0.0868 0.0261
2.35E-5
2.59E5
0.018 9.59E6
4.87E-6
2.32E5
0.594 8.58E6
1.61E-4
1.27E7
0.863 4.68E8
2.34E-4
6.15E9
7.98
2.29E11 2.16E-3
9.62E-13 0.613 3.56E-11 1.66E-4
2.86E5
N/A
1.06E7
N/A
1.56E5
N/A
5.78E6
N/A
0.047
0.104 1.75
2.81E-5
2.08E4
1.27
7.69E5
3.44E-4
2.00E6
7.03
7.40E7
1.90E-3
6.86E8
0.05
2.54E10 1.35E-5
4.61E6
N/A
1.71E8
N/A
76.4
0.0203 2.83E3
5.50E-6
39
Half-Life
13
N
9.965m
16
N
7.13s
22
Na
2.605y
24
Na
14.96h
94
Nb
2.03E5y
95
Nb
34.975d
144
Nd
2.29E15y
57
Ni
35.6h
59
Ni
7.60E4y
63
Ni
101y
65
Ni
2.52h
66
Ni
54.6h
237
Np
2.14E6y
238
Np
2.117d
239
Np
2.355d
240
Np
61.9m
15
O
122.2s
186
Os
2E15y
32
P
14.28d
33
P
25.34d
231
Pa
3.28E4y
233
Pa
26.967d
234
Pa
6.69h
234m
Pa
1.17m
209
Pb
3.253h
210
Pb
22.3y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.45E9
6.814 5.37E10 1.84E-3
9.89E10 16.57 3.66E12 4.48E-3
6.24E3
14.85 2.31E5
4.01E-3
8.73E6
20.55 3.23E8
5.55E-3
0.19
10.20 6.94
2.76E-3
3.93E4
4.74
1.46E6
1.28E-3
1.09E-12 N/A
4.02E-11 N/A
1.54E6
12
5.70E7
3.24E-3
0.080
12.5
2.95
3.38E-3
56.23
N/A
2.08E3
N/A
1.91E7
3.4
7.07E8
9.19E-4
8.71E5
N/A
3.22E7
N/A
7.05E-4 0.0868 0.0261
2.35E-5
2.59E5
0.018 9.59E6
4.87E-6
2.32E5
0.594 8.58E6
1.61E-4
1.27E7
0.863 4.68E8
2.34E-4
6.15E9
7.98
2.29E11 2.16E-3
9.62E-13 0.613 3.56E-11 1.66E-4
2.86E5
N/A
1.06E7
N/A
1.56E5
N/A
5.78E6
N/A
0.047
0.104 1.75
2.81E-5
2.08E4
1.27
7.69E5
3.44E-4
2.00E6
7.03
7.40E7
1.90E-3
6.86E8
0.05
2.54E10 1.35E-5
4.61E6
N/A
1.71E8
N/A
76.4
0.0203 2.83E3
5.50E-6
39
Half-Life
13
N
9.965m
16
N
7.13s
22
Na
2.605y
24
Na
14.96h
94
Nb
2.03E5y
95
Nb
34.975d
144
Nd
2.29E15y
57
Ni
35.6h
59
Ni
7.60E4y
63
Ni
101y
65
Ni
2.52h
66
Ni
54.6h
237
Np
2.14E6y
238
Np
2.117d
239
Np
2.355d
240
Np
61.9m
15
O
122.2s
186
Os
2E15y
32
P
14.28d
33
P
25.34d
231
Pa
3.28E4y
233
Pa
26.967d
234
Pa
6.69h
234m
Pa
1.17m
209
Pb
3.253h
210
Pb
22.3y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
1.45E9
6.814 5.37E10 1.84E-3
9.89E10 16.57 3.66E12 4.48E-3
6.24E3
14.85 2.31E5
4.01E-3
8.73E6
20.55 3.23E8
5.55E-3
0.19
10.20 6.94
2.76E-3
3.93E4
4.74
1.46E6
1.28E-3
1.09E-12 N/A
4.02E-11 N/A
1.54E6
12
5.70E7
3.24E-3
0.080
12.5
2.95
3.38E-3
56.23
N/A
2.08E3
N/A
1.91E7
3.4
7.07E8
9.19E-4
8.71E5
N/A
3.22E7
N/A
7.05E-4 0.0868 0.0261
2.35E-5
2.59E5
0.018 9.59E6
4.87E-6
2.32E5
0.594 8.58E6
1.61E-4
1.27E7
0.863 4.68E8
2.34E-4
6.15E9
7.98
2.29E11 2.16E-3
9.62E-13 0.613 3.56E-11 1.66E-4
2.86E5
N/A
1.06E7
N/A
1.56E5
N/A
5.78E6
N/A
0.047
0.104 1.75
2.81E-5
2.08E4
1.27
7.69E5
3.44E-4
2.00E6
7.03
7.40E7
1.90E-3
6.86E8
0.05
2.54E10 1.35E-5
4.61E6
N/A
1.71E8
N/A
76.4
0.0203 2.83E3
5.50E-6
39
211
Pb
212
Pb
214
Pb
107
Pd
147
Pm
149
Pm
151
Pm
210
Po
212
Po
214
Po
216
Po
218
Po
142m
Pr
190
Pt
202
Pt
236
Pu
238
Pu
239
Pu
240
Pu
241
Pu
242
Pu
223
Ra
224
Ra
225
Ra
226
Ra
228
Ra
211
Pb
212
Pb
214
Pb
107
Pd
147
Pm
149
Pm
151
Pm
210
Po
212
Po
214
Po
216
Po
218
Po
142m
Pr
190
Pt
202
Pt
236
Pu
238
Pu
239
Pu
240
Pu
241
Pu
242
Pu
223
Ra
224
Ra
225
Ra
226
Ra
228
Ra
Half-Life
36.1m
10.64h
27m
6.50E6y
2.6234y
53.08h
4.12m
138.38d
304ns
164us
145m s
3.10m
14.6m
6.50E11y
44.0h
2.87y
87.7y
2.41E4y
6560y
14.4y
3.75E5y
11.435d
3.66d
14.9d
1600y
5.76y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
2.47E7
0.248 9.14E8
6.71E-5
1.39E6
0.732 5.14E7
1.98E-4
3.25E7
1.155 1.20E9
3.12E-4
5.15E-4 N/A
0.0191
N/A
928.3
3.15E-5 3.43E4 8.53E-9
3.97E5
0.0532 1.47E7
1.44E-5
7.31E5
1.2
2.71E7
3.25E-4
4.49E3
N/A
1.66E5
N/A
1.78E17 N/A
6.59E18 N/A
3.22E14 6.71E-4 1.19E16 1.81E-7
3.60E11 9.95E-5 1.33E13 2.69E-9
2.78E8
N/A
1.03E10 N/A
9.08E7
N/A
3.36E9
N/A
2.90E-9 N/A
1.07E-7 N/A
3.53E5
N/A
1.30E7
N/A
528
N/A
1.95E4
N/A
17.1
N/A
633
N/A
0.062
2.11E-4 2.30
5.71E-8
0.227
N/A
8.40
N/A
103
N/A
3.81E3
N/A
3.94E-3 N/A
0.146
N/A
5.12E4
0.37
1.89E6
1.00E-4
1.59E5
0.054 5.88E6
1.46E-5
3.90E4
0.07
1.44E6
1.89E-5
0.99
0.045 36.6
1.22E-5
272
N/A
1.01E4
N/A
40
Half-Life
36.1m
10.64h
27m
6.50E6y
2.6234y
53.08h
4.12m
138.38d
304ns
164us
145m s
3.10m
14.6m
6.50E11y
44.0h
2.87y
87.7y
2.41E4y
6560y
14.4y
3.75E5y
11.435d
3.66d
14.9d
1600y
5.76y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
2.47E7
0.248 9.14E8
6.71E-5
1.39E6
0.732 5.14E7
1.98E-4
3.25E7
1.155 1.20E9
3.12E-4
5.15E-4 N/A
0.0191
N/A
928.3
3.15E-5 3.43E4 8.53E-9
3.97E5
0.0532 1.47E7
1.44E-5
7.31E5
1.2
2.71E7
3.25E-4
4.49E3
N/A
1.66E5
N/A
1.78E17 N/A
6.59E18 N/A
3.22E14 6.71E-4 1.19E16 1.81E-7
3.60E11 9.95E-5 1.33E13 2.69E-9
2.78E8
N/A
1.03E10 N/A
9.08E7
N/A
3.36E9
N/A
2.90E-9 N/A
1.07E-7 N/A
3.53E5
N/A
1.30E7
N/A
528
N/A
1.95E4
N/A
17.1
N/A
633
N/A
0.062
2.11E-4 2.30
5.71E-8
0.227
N/A
8.40
N/A
103
N/A
3.81E3
N/A
3.94E-3 N/A
0.146
N/A
5.12E4
0.37
1.89E6
1.00E-4
1.59E5
0.054 5.88E6
1.46E-5
3.90E4
0.07
1.44E6
1.89E-5
0.99
0.045 36.6
1.22E-5
272
N/A
1.01E4
N/A
40
211
Pb
212
Pb
214
Pb
107
Pd
147
Pm
149
Pm
151
Pm
210
Po
212
Po
214
Po
216
Po
218
Po
142m
Pr
190
Pt
202
Pt
236
Pu
238
Pu
239
Pu
240
Pu
241
Pu
242
Pu
223
Ra
224
Ra
225
Ra
226
Ra
228
Ra
211
Pb
212
Pb
214
Pb
107
Pd
147
Pm
149
Pm
151
Pm
210
Po
212
Po
214
Po
216
Po
218
Po
142m
Pr
190
Pt
202
Pt
236
Pu
238
Pu
239
Pu
240
Pu
241
Pu
242
Pu
223
Ra
224
Ra
225
Ra
226
Ra
228
Ra
Half-Life
36.1m
10.64h
27m
6.50E6y
2.6234y
53.08h
4.12m
138.38d
304ns
164us
145m s
3.10m
14.6m
6.50E11y
44.0h
2.87y
87.7y
2.41E4y
6560y
14.4y
3.75E5y
11.435d
3.66d
14.9d
1600y
5.76y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
2.47E7
0.248 9.14E8
6.71E-5
1.39E6
0.732 5.14E7
1.98E-4
3.25E7
1.155 1.20E9
3.12E-4
5.15E-4 N/A
0.0191
N/A
928.3
3.15E-5 3.43E4 8.53E-9
3.97E5
0.0532 1.47E7
1.44E-5
7.31E5
1.2
2.71E7
3.25E-4
4.49E3
N/A
1.66E5
N/A
1.78E17 N/A
6.59E18 N/A
3.22E14 6.71E-4 1.19E16 1.81E-7
3.60E11 9.95E-5 1.33E13 2.69E-9
2.78E8
N/A
1.03E10 N/A
9.08E7
N/A
3.36E9
N/A
2.90E-9 N/A
1.07E-7 N/A
3.53E5
N/A
1.30E7
N/A
528
N/A
1.95E4
N/A
17.1
N/A
633
N/A
0.062
2.11E-4 2.30
5.71E-8
0.227
N/A
8.40
N/A
103
N/A
3.81E3
N/A
3.94E-3 N/A
0.146
N/A
5.12E4
0.37
1.89E6
1.00E-4
1.59E5
0.054 5.88E6
1.46E-5
3.90E4
0.07
1.44E6
1.89E-5
0.99
0.045 36.6
1.22E-5
272
N/A
1.01E4
N/A
40
Half-Life
36.1m
10.64h
27m
6.50E6y
2.6234y
53.08h
4.12m
138.38d
304ns
164us
145m s
3.10m
14.6m
6.50E11y
44.0h
2.87y
87.7y
2.41E4y
6560y
14.4y
3.75E5y
11.435d
3.66d
14.9d
1600y
5.76y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
2.47E7
0.248 9.14E8
6.71E-5
1.39E6
0.732 5.14E7
1.98E-4
3.25E7
1.155 1.20E9
3.12E-4
5.15E-4 N/A
0.0191
N/A
928.3
3.15E-5 3.43E4 8.53E-9
3.97E5
0.0532 1.47E7
1.44E-5
7.31E5
1.2
2.71E7
3.25E-4
4.49E3
N/A
1.66E5
N/A
1.78E17 N/A
6.59E18 N/A
3.22E14 6.71E-4 1.19E16 1.81E-7
3.60E11 9.95E-5 1.33E13 2.69E-9
2.78E8
N/A
1.03E10 N/A
9.08E7
N/A
3.36E9
N/A
2.90E-9 N/A
1.07E-7 N/A
3.53E5
N/A
1.30E7
N/A
528
N/A
1.95E4
N/A
17.1
N/A
633
N/A
0.062
2.11E-4 2.30
5.71E-8
0.227
N/A
8.40
N/A
103
N/A
3.81E3
N/A
3.94E-3 N/A
0.146
N/A
5.12E4
0.37
1.89E6
1.00E-4
1.59E5
0.054 5.88E6
1.46E-5
3.90E4
0.07
1.44E6
1.89E-5
0.99
0.045 36.6
1.22E-5
272
N/A
1.01E4
N/A
40
81
Rb
82
Rb
83
Rb
87
Rb
88
Rb
89
Rb
187
Re
188
Re
105
Rh
106
Rh
212
Rn
216
Rn
219
Rn
220
Rn
222
Rn
97
Ru
103
Ru
105
Ru
106
Ru
35
S
122
Sb
124
Sb
125
Sb
126
Sb
44
Sc
46
Sc
81
Rb
82
Rb
83
Rb
87
Rb
88
Rb
89
Rb
187
Re
188
Re
105
Rh
106
Rh
212
Rn
216
Rn
219
Rn
220
Rn
222
Rn
97
Ru
103
Ru
105
Ru
106
Ru
35
S
122
Sb
124
Sb
125
Sb
126
Sb
44
Sc
46
Sc
Half-Life
4.576h
1.273m
86.2d
4.75E10y
17.7m
15.4m
4.35E10y
16.98h
35.36h
29.8s
23.9m
45.0us
3.96s
55.6s
3.8235d
2.9d
39.26d
4.44h
1.02y
87.51d
2.7238d
60.2d
1007.4d
12.46d
3.927h
83.81d
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
8.47E6
3.628 3.13E8
9.82E-4
1.80E9
7.452 6.67E10 2.02E-3
1.83E4
3.135 6.76E5
8.49E-4
8.67E-8 N/A
3.21E-6 N/A
1.21E8
3.58
4.48E9
9.68E-4
1.37E8
12.17 5.07E9
3.29E-3
4.40E-8 N/A
1.63E-6 N/A
9.82E5
0.2096 3.63E7
5.67E-5
8.45E5
0.462 3.13E7
1.25E-4
3.58E9
0.644 1.32E11 1.74E-4
3.71E7
N/A
1.37E9
N/A
1.16E15 N/A
4.30E16 N/A
1.30E10 0.329 4.81E11 8.91E-5
9.21E8
3.99E-3 3.41E10 1.08E-6
1.54E5
3.03E-3 5.70E6 8.19E-7
4.65E5
1.32
1.72E7
3.57E-4
3.23E4
2.65
1.20E6
7.17E-4
6.73E6
1.93
2.49E8
5.22E-4
3.31E3
N/A
1.22E5
N/A
4.27E4
N/A
1.58E6
N/A
3.93E5
2.991 1.46E7
8.10E-4
1.75E4
9.62
6.48E5
2.60E-3
1.04E3
2.57
3.84E4
6.96E-4
8.33E4
11.5
3.08E6
3.11E-3
1.82E7
0.579 6.72E8
1.57E-4
3.39E4
10.9
1.25E6
2.95E-3
41
Half-Life
4.576h
1.273m
86.2d
4.75E10y
17.7m
15.4m
4.35E10y
16.98h
35.36h
29.8s
23.9m
45.0us
3.96s
55.6s
3.8235d
2.9d
39.26d
4.44h
1.02y
87.51d
2.7238d
60.2d
1007.4d
12.46d
3.927h
83.81d
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
8.47E6
3.628 3.13E8
9.82E-4
1.80E9
7.452 6.67E10 2.02E-3
1.83E4
3.135 6.76E5
8.49E-4
8.67E-8 N/A
3.21E-6 N/A
1.21E8
3.58
4.48E9
9.68E-4
1.37E8
12.17 5.07E9
3.29E-3
4.40E-8 N/A
1.63E-6 N/A
9.82E5
0.2096 3.63E7
5.67E-5
8.45E5
0.462 3.13E7
1.25E-4
3.58E9
0.644 1.32E11 1.74E-4
3.71E7
N/A
1.37E9
N/A
1.16E15 N/A
4.30E16 N/A
1.30E10 0.329 4.81E11 8.91E-5
9.21E8
3.99E-3 3.41E10 1.08E-6
1.54E5
3.03E-3 5.70E6 8.19E-7
4.65E5
1.32
1.72E7
3.57E-4
3.23E4
2.65
1.20E6
7.17E-4
6.73E6
1.93
2.49E8
5.22E-4
3.31E3
N/A
1.22E5
N/A
4.27E4
N/A
1.58E6
N/A
3.93E5
2.991 1.46E7
8.10E-4
1.75E4
9.62
6.48E5
2.60E-3
1.04E3
2.57
3.84E4
6.96E-4
8.33E4
11.5
3.08E6
3.11E-3
1.82E7
0.579 6.72E8
1.57E-4
3.39E4
10.9
1.25E6
2.95E-3
41
81
Rb
82
Rb
83
Rb
87
Rb
88
Rb
89
Rb
187
Re
188
Re
105
Rh
106
Rh
212
Rn
216
Rn
219
Rn
220
Rn
222
Rn
97
Ru
103
Ru
105
Ru
106
Ru
35
S
122
Sb
124
Sb
125
Sb
126
Sb
44
Sc
46
Sc
81
Rb
82
Rb
83
Rb
87
Rb
88
Rb
89
Rb
187
Re
188
Re
105
Rh
106
Rh
212
Rn
216
Rn
219
Rn
220
Rn
222
Rn
97
Ru
103
Ru
105
Ru
106
Ru
35
S
122
Sb
124
Sb
125
Sb
126
Sb
44
Sc
46
Sc
Half-Life
4.576h
1.273m
86.2d
4.75E10y
17.7m
15.4m
4.35E10y
16.98h
35.36h
29.8s
23.9m
45.0us
3.96s
55.6s
3.8235d
2.9d
39.26d
4.44h
1.02y
87.51d
2.7238d
60.2d
1007.4d
12.46d
3.927h
83.81d
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
8.47E6
3.628 3.13E8
9.82E-4
1.80E9
7.452 6.67E10 2.02E-3
1.83E4
3.135 6.76E5
8.49E-4
8.67E-8 N/A
3.21E-6 N/A
1.21E8
3.58
4.48E9
9.68E-4
1.37E8
12.17 5.07E9
3.29E-3
4.40E-8 N/A
1.63E-6 N/A
9.82E5
0.2096 3.63E7
5.67E-5
8.45E5
0.462 3.13E7
1.25E-4
3.58E9
0.644 1.32E11 1.74E-4
3.71E7
N/A
1.37E9
N/A
1.16E15 N/A
4.30E16 N/A
1.30E10 0.329 4.81E11 8.91E-5
9.21E8
3.99E-3 3.41E10 1.08E-6
1.54E5
3.03E-3 5.70E6 8.19E-7
4.65E5
1.32
1.72E7
3.57E-4
3.23E4
2.65
1.20E6
7.17E-4
6.73E6
1.93
2.49E8
5.22E-4
3.31E3
N/A
1.22E5
N/A
4.27E4
N/A
1.58E6
N/A
3.93E5
2.991 1.46E7
8.10E-4
1.75E4
9.62
6.48E5
2.60E-3
1.04E3
2.57
3.84E4
6.96E-4
8.33E4
11.5
3.08E6
3.11E-3
1.82E7
0.579 6.72E8
1.57E-4
3.39E4
10.9
1.25E6
2.95E-3
41
Half-Life
4.576h
1.273m
86.2d
4.75E10y
17.7m
15.4m
4.35E10y
16.98h
35.36h
29.8s
23.9m
45.0us
3.96s
55.6s
3.8235d
2.9d
39.26d
4.44h
1.02y
87.51d
2.7238d
60.2d
1007.4d
12.46d
3.927h
83.81d
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
8.47E6
3.628 3.13E8
9.82E-4
1.80E9
7.452 6.67E10 2.02E-3
1.83E4
3.135 6.76E5
8.49E-4
8.67E-8 N/A
3.21E-6 N/A
1.21E8
3.58
4.48E9
9.68E-4
1.37E8
12.17 5.07E9
3.29E-3
4.40E-8 N/A
1.63E-6 N/A
9.82E5
0.2096 3.63E7
5.67E-5
8.45E5
0.462 3.13E7
1.25E-4
3.58E9
0.644 1.32E11 1.74E-4
3.71E7
N/A
1.37E9
N/A
1.16E15 N/A
4.30E16 N/A
1.30E10 0.329 4.81E11 8.91E-5
9.21E8
3.99E-3 3.41E10 1.08E-6
1.54E5
3.03E-3 5.70E6 8.19E-7
4.65E5
1.32
1.72E7
3.57E-4
3.23E4
2.65
1.20E6
7.17E-4
6.73E6
1.93
2.49E8
5.22E-4
3.31E3
N/A
1.22E5
N/A
4.27E4
N/A
1.58E6
N/A
3.93E5
2.991 1.46E7
8.10E-4
1.75E4
9.62
6.48E5
2.60E-3
1.04E3
2.57
3.84E4
6.96E-4
8.33E4
11.5
3.08E6
3.11E-3
1.82E7
0.579 6.72E8
1.57E-4
3.39E4
10.9
1.25E6
2.95E-3
41
Half-Life
47
Sc
3.349d
48
Sc
43.7h
75
Se
119.78d
79
Se
6.50E5y
32
Si
132y
146
Sm
1.031E8y
147
Sm
1.06E11y
148
Sm
7.00E15y
153
Sm
46.27h
121
Sn
27.06h
125
Sn
9.64d
85
Sr
64.84d
87m
Sr
2.803h
89
Sr
50.52d
90
Sr
29.1y
91
Sr
9.63h
92
Sr
2.71h
160
Tb
72.3d
99
Tc
2.13E5y
99m
Tc
6.01h
101
Tc
14.2m
123m
Te
119.7d
127
Te
9.35h
129
Te
69.6m
129m
Te
33.6d
131
Te
25m
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
8.30E5
0.56
3.07E7
1.51E-4
1.49E6
21
5.51E7
5.68E-3
1.45E4
9.53
5.37E5
2.58E-3
6.98E-3 N/A
0.258
N/A
84.77
N/A
3.14E3
N/A
2.38E-5 N/A
8.80E-4 N/A
2.30E-8 N/A
8.50E-7 N/A
3.46E-13 N/A
1.28E-11 N/A
4.43E5
0.175 1.64E7
4.74E-5
9.58E5
N/A
3.54E7
N/A
1.09E5
0.33
4.01E6
8.93E-5
2.37E4
3.06
8.78E5
8.28E-4
1.32E7
1.92
4.87E8
5.20E-4
2.90E4
5.29E-3 1.07E6 1.43E-6
137.0
N/A
5.07E3
N/A
3.58E6
0.635 1.32E8
1.72E-4
1.26E7
7.8942 4.65E8
2.14E-3
1.13E4
0.635 4.18E5
1.72E-4
0.017
N/A
0.629
N/A
5.27E6
0.896 1.95E8
2.42E-4
1.31E8
1.71
4.85E9
4.63E-4
8.88E3
1.365 3.28E5
3.69E-4
2.64E6
0.0335 9.78E7
9.06E-6
2.10E7
0.5717 7.76E8
1.55E-4
3.02E4
0.137 1.12E6
3.71E-5
5.75E7
1.57
2.13E9
4.25E-4
42
Half-Life
47
Sc
3.349d
48
Sc
43.7h
75
Se
119.78d
79
Se
6.50E5y
32
Si
132y
146
Sm
1.031E8y
147
Sm
1.06E11y
148
Sm
7.00E15y
153
Sm
46.27h
121
Sn
27.06h
125
Sn
9.64d
85
Sr
64.84d
87m
Sr
2.803h
89
Sr
50.52d
90
Sr
29.1y
91
Sr
9.63h
92
Sr
2.71h
160
Tb
72.3d
99
Tc
2.13E5y
99m
Tc
6.01h
101
Tc
14.2m
123m
Te
119.7d
127
Te
9.35h
129
Te
69.6m
129m
Te
33.6d
131
Te
25m
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
8.30E5
0.56
3.07E7
1.51E-4
1.49E6
21
5.51E7
5.68E-3
1.45E4
9.53
5.37E5
2.58E-3
6.98E-3 N/A
0.258
N/A
84.77
N/A
3.14E3
N/A
2.38E-5 N/A
8.80E-4 N/A
2.30E-8 N/A
8.50E-7 N/A
3.46E-13 N/A
1.28E-11 N/A
4.43E5
0.175 1.64E7
4.74E-5
9.58E5
N/A
3.54E7
N/A
1.09E5
0.33
4.01E6
8.93E-5
2.37E4
3.06
8.78E5
8.28E-4
1.32E7
1.92
4.87E8
5.20E-4
2.90E4
5.29E-3 1.07E6 1.43E-6
137.0
N/A
5.07E3
N/A
3.58E6
0.635 1.32E8
1.72E-4
1.26E7
7.8942 4.65E8
2.14E-3
1.13E4
0.635 4.18E5
1.72E-4
0.017
N/A
0.629
N/A
5.27E6
0.896 1.95E8
2.42E-4
1.31E8
1.71
4.85E9
4.63E-4
8.88E3
1.365 3.28E5
3.69E-4
2.64E6
0.0335 9.78E7
9.06E-6
2.10E7
0.5717 7.76E8
1.55E-4
3.02E4
0.137 1.12E6
3.71E-5
5.75E7
1.57
2.13E9
4.25E-4
42
Half-Life
47
Sc
3.349d
48
Sc
43.7h
75
Se
119.78d
79
Se
6.50E5y
32
Si
132y
146
Sm
1.031E8y
147
Sm
1.06E11y
148
Sm
7.00E15y
153
Sm
46.27h
121
Sn
27.06h
125
Sn
9.64d
85
Sr
64.84d
87m
Sr
2.803h
89
Sr
50.52d
90
Sr
29.1y
91
Sr
9.63h
92
Sr
2.71h
160
Tb
72.3d
99
Tc
2.13E5y
99m
Tc
6.01h
101
Tc
14.2m
123m
Te
119.7d
127
Te
9.35h
129
Te
69.6m
129m
Te
33.6d
131
Te
25m
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
8.30E5
0.56
3.07E7
1.51E-4
1.49E6
21
5.51E7
5.68E-3
1.45E4
9.53
5.37E5
2.58E-3
6.98E-3 N/A
0.258
N/A
84.77
N/A
3.14E3
N/A
2.38E-5 N/A
8.80E-4 N/A
2.30E-8 N/A
8.50E-7 N/A
3.46E-13 N/A
1.28E-11 N/A
4.43E5
0.175 1.64E7
4.74E-5
9.58E5
N/A
3.54E7
N/A
1.09E5
0.33
4.01E6
8.93E-5
2.37E4
3.06
8.78E5
8.28E-4
1.32E7
1.92
4.87E8
5.20E-4
2.90E4
5.29E-3 1.07E6 1.43E-6
137.0
N/A
5.07E3
N/A
3.58E6
0.635 1.32E8
1.72E-4
1.26E7
7.8942 4.65E8
2.14E-3
1.13E4
0.635 4.18E5
1.72E-4
0.017
N/A
0.629
N/A
5.27E6
0.896 1.95E8
2.42E-4
1.31E8
1.71
4.85E9
4.63E-4
8.88E3
1.365 3.28E5
3.69E-4
2.64E6
0.0335 9.78E7
9.06E-6
2.10E7
0.5717 7.76E8
1.55E-4
3.02E4
0.137 1.12E6
3.71E-5
5.75E7
1.57
2.13E9
4.25E-4
42
Half-Life
47
Sc
3.349d
48
Sc
43.7h
75
Se
119.78d
79
Se
6.50E5y
32
Si
132y
146
Sm
1.031E8y
147
Sm
1.06E11y
148
Sm
7.00E15y
153
Sm
46.27h
121
Sn
27.06h
125
Sn
9.64d
85
Sr
64.84d
87m
Sr
2.803h
89
Sr
50.52d
90
Sr
29.1y
91
Sr
9.63h
92
Sr
2.71h
160
Tb
72.3d
99
Tc
2.13E5y
99m
Tc
6.01h
101
Tc
14.2m
123m
Te
119.7d
127
Te
9.35h
129
Te
69.6m
129m
Te
33.6d
131
Te
25m
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
8.30E5
0.56
3.07E7
1.51E-4
1.49E6
21
5.51E7
5.68E-3
1.45E4
9.53
5.37E5
2.58E-3
6.98E-3 N/A
0.258
N/A
84.77
N/A
3.14E3
N/A
2.38E-5 N/A
8.80E-4 N/A
2.30E-8 N/A
8.50E-7 N/A
3.46E-13 N/A
1.28E-11 N/A
4.43E5
0.175 1.64E7
4.74E-5
9.58E5
N/A
3.54E7
N/A
1.09E5
0.33
4.01E6
8.93E-5
2.37E4
3.06
8.78E5
8.28E-4
1.32E7
1.92
4.87E8
5.20E-4
2.90E4
5.29E-3 1.07E6 1.43E-6
137.0
N/A
5.07E3
N/A
3.58E6
0.635 1.32E8
1.72E-4
1.26E7
7.8942 4.65E8
2.14E-3
1.13E4
0.635 4.18E5
1.72E-4
0.017
N/A
0.629
N/A
5.27E6
0.896 1.95E8
2.42E-4
1.31E8
1.71
4.85E9
4.63E-4
8.88E3
1.365 3.28E5
3.69E-4
2.64E6
0.0335 9.78E7
9.06E-6
2.10E7
0.5717 7.76E8
1.55E-4
3.02E4
0.137 1.12E6
3.71E-5
5.75E7
1.57
2.13E9
4.25E-4
42
Half-Life
131m
Te
30h
132
Te
3.204d
133
Te
12.5m
133m
Te
55.4m
134
Te
41.8m
135
Te
19s
227
Th
18.72d
228
Th
1.913y
229
Th
7300y
230
Th
7.54E4y
231
Th
25.55h
232
Th
1.40E10y
234
Th
24.10d
201
Tl
72.912h
204
Tl
3.78y
206
Tl
4.20m
208
Tl
3.053m
209
Tl
2.161m
210
Tl
1.30m
230
U
20.8d
232
U
70y
233
U
1.592E5y
234
U
2.46E5y
235
U
7.04E8y
235m
U
25.0m
236
U
2.342E7y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
7.98E5
2.18
2.95E7
5.90E-4
3.09E5
2.124 1.14E7
5.75E-4
1.13E8
2.32
4.19E9
6.28E-4
2.55E7
3.11
9.45E8
8.42E-4
3.36E7
1.77
1.24E9
4.79E-4
4.40E9
0.195 1.63E11 5.28E-5
3.07E4
0.39
1.14E6
1.05E-4
820.0
0.014 3.03E4
3.78E-6
0.214
0.145 7.92
3.92E-5
0.021
2.07E-3 0.762
5.60E-7
5.32E5
0.0480 1.97E7
1.30E-5
1.10E-7 7.62E-4 4.07E-6 2.06E-7
2.32E4
0.0356 8.58E5
9.62E-6
2.14E5
0.122 7.91E6
3.30E-5
464.0
0.0124 1.72E4
3.35E-6
2.17E8
N/A
8.03E9
N/A
2.96E8
18.89 1.10E10 5.11E-3
4.16E8
4.17
1.54E10 1.13E-3
6.88E8
7.82
2.55E10 2.11E-3
2.73E4
2.00E-3 1.01E6 5.41E-7
22.0
0.0731 814
1.98E-5
9.65E-3 N/A
0.357
N/A
6.22E-3 N/A
0.230
N/A
2.16E-6 0.755 7.99E-5 2.04E-4
3.20E7
N/A
1.18E9
N/A
6.47E-5 1.10E-4 2.40E-3 2.98E-8
43
Half-Life
131m
Te
30h
132
Te
3.204d
133
Te
12.5m
133m
Te
55.4m
134
Te
41.8m
135
Te
19s
227
Th
18.72d
228
Th
1.913y
229
Th
7300y
230
Th
7.54E4y
231
Th
25.55h
232
Th
1.40E10y
234
Th
24.10d
201
Tl
72.912h
204
Tl
3.78y
206
Tl
4.20m
208
Tl
3.053m
209
Tl
2.161m
210
Tl
1.30m
230
U
20.8d
232
U
70y
233
U
1.592E5y
234
U
2.46E5y
235
U
7.04E8y
235m
U
25.0m
236
U
2.342E7y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
7.98E5
2.18
2.95E7
5.90E-4
3.09E5
2.124 1.14E7
5.75E-4
1.13E8
2.32
4.19E9
6.28E-4
2.55E7
3.11
9.45E8
8.42E-4
3.36E7
1.77
1.24E9
4.79E-4
4.40E9
0.195 1.63E11 5.28E-5
3.07E4
0.39
1.14E6
1.05E-4
820.0
0.014 3.03E4
3.78E-6
0.214
0.145 7.92
3.92E-5
0.021
2.07E-3 0.762
5.60E-7
5.32E5
0.0480 1.97E7
1.30E-5
1.10E-7 7.62E-4 4.07E-6 2.06E-7
2.32E4
0.0356 8.58E5
9.62E-6
2.14E5
0.122 7.91E6
3.30E-5
464.0
0.0124 1.72E4
3.35E-6
2.17E8
N/A
8.03E9
N/A
2.96E8
18.89 1.10E10 5.11E-3
4.16E8
4.17
1.54E10 1.13E-3
6.88E8
7.82
2.55E10 2.11E-3
2.73E4
2.00E-3 1.01E6 5.41E-7
22.0
0.0731 814
1.98E-5
9.65E-3 N/A
0.357
N/A
6.22E-3 N/A
0.230
N/A
2.16E-6 0.755 7.99E-5 2.04E-4
3.20E7
N/A
1.18E9
N/A
6.47E-5 1.10E-4 2.40E-3 2.98E-8
43
Half-Life
131m
Te
30h
132
Te
3.204d
133
Te
12.5m
133m
Te
55.4m
134
Te
41.8m
135
Te
19s
227
Th
18.72d
228
Th
1.913y
229
Th
7300y
230
Th
7.54E4y
231
Th
25.55h
232
Th
1.40E10y
234
Th
24.10d
201
Tl
72.912h
204
Tl
3.78y
206
Tl
4.20m
208
Tl
3.053m
209
Tl
2.161m
210
Tl
1.30m
230
U
20.8d
232
U
70y
233
U
1.592E5y
234
U
2.46E5y
235
U
7.04E8y
235m
U
25.0m
236
U
2.342E7y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
7.98E5
2.18
2.95E7
5.90E-4
3.09E5
2.124 1.14E7
5.75E-4
1.13E8
2.32
4.19E9
6.28E-4
2.55E7
3.11
9.45E8
8.42E-4
3.36E7
1.77
1.24E9
4.79E-4
4.40E9
0.195 1.63E11 5.28E-5
3.07E4
0.39
1.14E6
1.05E-4
820.0
0.014 3.03E4
3.78E-6
0.214
0.145 7.92
3.92E-5
0.021
2.07E-3 0.762
5.60E-7
5.32E5
0.0480 1.97E7
1.30E-5
1.10E-7 7.62E-4 4.07E-6 2.06E-7
2.32E4
0.0356 8.58E5
9.62E-6
2.14E5
0.122 7.91E6
3.30E-5
464.0
0.0124 1.72E4
3.35E-6
2.17E8
N/A
8.03E9
N/A
2.96E8
18.89 1.10E10 5.11E-3
4.16E8
4.17
1.54E10 1.13E-3
6.88E8
7.82
2.55E10 2.11E-3
2.73E4
2.00E-3 1.01E6 5.41E-7
22.0
0.0731 814
1.98E-5
9.65E-3 N/A
0.357
N/A
6.22E-3 N/A
0.230
N/A
2.16E-6 0.755 7.99E-5 2.04E-4
3.20E7
N/A
1.18E9
N/A
6.47E-5 1.10E-4 2.40E-3 2.98E-8
43
Half-Life
131m
Te
30h
132
Te
3.204d
133
Te
12.5m
133m
Te
55.4m
134
Te
41.8m
135
Te
19s
227
Th
18.72d
228
Th
1.913y
229
Th
7300y
230
Th
7.54E4y
231
Th
25.55h
232
Th
1.40E10y
234
Th
24.10d
201
Tl
72.912h
204
Tl
3.78y
206
Tl
4.20m
208
Tl
3.053m
209
Tl
2.161m
210
Tl
1.30m
230
U
20.8d
232
U
70y
233
U
1.592E5y
234
U
2.46E5y
235
U
7.04E8y
235m
U
25.0m
236
U
2.342E7y
Rem /hr / Ci
Sv/hr / GBq
Ci/g
@ 30 cm GBq/g @ 30cm
7.98E5
2.18
2.95E7
5.90E-4
3.09E5
2.124 1.14E7
5.75E-4
1.13E8
2.32
4.19E9
6.28E-4
2.55E7
3.11
9.45E8
8.42E-4
3.36E7
1.77
1.24E9
4.79E-4
4.40E9
0.195 1.63E11 5.28E-5
3.07E4
0.39
1.14E6
1.05E-4
820.0
0.014 3.03E4
3.78E-6
0.214
0.145 7.92
3.92E-5
0.021
2.07E-3 0.762
5.60E-7
5.32E5
0.0480 1.97E7
1.30E-5
1.10E-7 7.62E-4 4.07E-6 2.06E-7
2.32E4
0.0356 8.58E5
9.62E-6
2.14E5
0.122 7.91E6
3.30E-5
464.0
0.0124 1.72E4
3.35E-6
2.17E8
N/A
8.03E9
N/A
2.96E8
18.89 1.10E10 5.11E-3
4.16E8
4.17
1.54E10 1.13E-3
6.88E8
7.82
2.55E10 2.11E-3
2.73E4
2.00E-3 1.01E6 5.41E-7
22.0
0.0731 814
1.98E-5
9.65E-3 N/A
0.357
N/A
6.22E-3 N/A
0.230
N/A
2.16E-6 0.755 7.99E-5 2.04E-4
3.20E7
N/A
1.18E9
N/A
6.47E-5 1.10E-4 2.40E-3 2.98E-8
43
Rem /hr / Ci
Sv/hr / GBq
Half-Life
Ci/g
@ 30 cm GBq/g @ 30cm
237
U
6.75d
8.16E4
0.561 3.02E6
1.52E-4
238
U
4.47E9y
3.36E-7 N/A
1.24E-5 N/A
48
V
15.98d
1.70E5
15.6
6.29E6
4.22E-3
49
V
330d
8.09E3
N/A
2.99E5
N/A
187
W
23.72d
7.07E5
2.82
2.62E7
7.63E-4
131m
Xe
11.84d
8.69E4
0.5664 3.22E6
1.53E-4
133
Xe
5.243d
1.87E5
0.6248 6.93E6
1.69E-4
133m
Xe
2.19d
4.49E5
0.7027 1.66E7
1.90E-4
135
Xe
9.14h
2.54E6
1.6178 9.41E7
4.38E-4
135m
Xe
15.29m
9.12E7
2.9736 3.37E9
8.05E-4
138
Xe
14.08m
9.69E7
1.36
3.58E9
3.68E-4
88
Y
106.65d
1.39E4
14.83 5.15E5
4.01E-3
90
Y
64.1h
5.43E5
N/A
2.01E7
N/A
92
Y
3.54h
9.63E6
0.126 3.56E8
3.41E-5
93
Y
10.18h
3.31E6
0.11
1.23E8
2.98E-5
169
Yb
32.026d
2.41E4
1.219 8.93E5
3.30E-4
65
Zn
243.8d
8.24E3
3.575 3.05E5
9.68E-4
89
Zr
78.41h
4.50E5
5.65
1.66E7
1.53E-3
93
Zr
1.53E6y
2.52E-3 N/A
0.0931
N/A
95
Zr
64.02d
2.15E4
5.16
7.96E5
1.39E-3
97
Zr
16.91h
1.91E6
0.236 7.08E7
6.39E-5
The exposure rate from these radionuclides do not
include their short-lived progeny. Spontaneous fission,
isotopic m ixtures, im purities in m ixtures, and shielding
(including self shielding) should also be taken into
account when estim ating exposure rate.
44
Rem /hr / Ci
Sv/hr / GBq
Half-Life
Ci/g
@ 30 cm GBq/g @ 30cm
237
U
6.75d
8.16E4
0.561 3.02E6
1.52E-4
238
U
4.47E9y
3.36E-7 N/A
1.24E-5 N/A
48
V
15.98d
1.70E5
15.6
6.29E6
4.22E-3
49
V
330d
8.09E3
N/A
2.99E5
N/A
187
W
23.72d
7.07E5
2.82
2.62E7
7.63E-4
131m
Xe
11.84d
8.69E4
0.5664 3.22E6
1.53E-4
133
Xe
5.243d
1.87E5
0.6248 6.93E6
1.69E-4
133m
Xe
2.19d
4.49E5
0.7027 1.66E7
1.90E-4
135
Xe
9.14h
2.54E6
1.6178 9.41E7
4.38E-4
135m
Xe
15.29m
9.12E7
2.9736 3.37E9
8.05E-4
138
Xe
14.08m
9.69E7
1.36
3.58E9
3.68E-4
88
Y
106.65d
1.39E4
14.83 5.15E5
4.01E-3
90
Y
64.1h
5.43E5
N/A
2.01E7
N/A
92
Y
3.54h
9.63E6
0.126 3.56E8
3.41E-5
93
Y
10.18h
3.31E6
0.11
1.23E8
2.98E-5
169
Yb
32.026d
2.41E4
1.219 8.93E5
3.30E-4
65
Zn
243.8d
8.24E3
3.575 3.05E5
9.68E-4
89
Zr
78.41h
4.50E5
5.65
1.66E7
1.53E-3
93
Zr
1.53E6y
2.52E-3 N/A
0.0931
N/A
95
Zr
64.02d
2.15E4
5.16
7.96E5
1.39E-3
97
Zr
16.91h
1.91E6
0.236 7.08E7
6.39E-5
The exposure rate from these radionuclides do not
include their short-lived progeny. Spontaneous fission,
isotopic m ixtures, im purities in m ixtures, and shielding
(including self shielding) should also be taken into
account when estim ating exposure rate.
44
Rem /hr / Ci
Sv/hr / GBq
Half-Life
Ci/g
@ 30 cm GBq/g @ 30cm
237
U
6.75d
8.16E4
0.561 3.02E6
1.52E-4
238
U
4.47E9y
3.36E-7 N/A
1.24E-5 N/A
48
V
15.98d
1.70E5
15.6
6.29E6
4.22E-3
49
V
330d
8.09E3
N/A
2.99E5
N/A
187
W
23.72d
7.07E5
2.82
2.62E7
7.63E-4
131m
Xe
11.84d
8.69E4
0.5664 3.22E6
1.53E-4
133
Xe
5.243d
1.87E5
0.6248 6.93E6
1.69E-4
133m
Xe
2.19d
4.49E5
0.7027 1.66E7
1.90E-4
135
Xe
9.14h
2.54E6
1.6178 9.41E7
4.38E-4
135m
Xe
15.29m
9.12E7
2.9736 3.37E9
8.05E-4
138
Xe
14.08m
9.69E7
1.36
3.58E9
3.68E-4
88
Y
106.65d
1.39E4
14.83 5.15E5
4.01E-3
90
Y
64.1h
5.43E5
N/A
2.01E7
N/A
92
Y
3.54h
9.63E6
0.126 3.56E8
3.41E-5
93
Y
10.18h
3.31E6
0.11
1.23E8
2.98E-5
169
Yb
32.026d
2.41E4
1.219 8.93E5
3.30E-4
65
Zn
243.8d
8.24E3
3.575 3.05E5
9.68E-4
89
Zr
78.41h
4.50E5
5.65
1.66E7
1.53E-3
93
Zr
1.53E6y
2.52E-3 N/A
0.0931
N/A
95
Zr
64.02d
2.15E4
5.16
7.96E5
1.39E-3
97
Zr
16.91h
1.91E6
0.236 7.08E7
6.39E-5
The exposure rate from these radionuclides do not
include their short-lived progeny. Spontaneous fission,
isotopic m ixtures, im purities in m ixtures, and shielding
(including self shielding) should also be taken into
account when estim ating exposure rate.
44
Rem /hr / Ci
Sv/hr / GBq
Half-Life
Ci/g
@ 30 cm GBq/g @ 30cm
237
U
6.75d
8.16E4
0.561 3.02E6
1.52E-4
238
U
4.47E9y
3.36E-7 N/A
1.24E-5 N/A
48
V
15.98d
1.70E5
15.6
6.29E6
4.22E-3
49
V
330d
8.09E3
N/A
2.99E5
N/A
187
W
23.72d
7.07E5
2.82
2.62E7
7.63E-4
131m
Xe
11.84d
8.69E4
0.5664 3.22E6
1.53E-4
133
Xe
5.243d
1.87E5
0.6248 6.93E6
1.69E-4
133m
Xe
2.19d
4.49E5
0.7027 1.66E7
1.90E-4
135
Xe
9.14h
2.54E6
1.6178 9.41E7
4.38E-4
135m
Xe
15.29m
9.12E7
2.9736 3.37E9
8.05E-4
138
Xe
14.08m
9.69E7
1.36
3.58E9
3.68E-4
88
Y
106.65d
1.39E4
14.83 5.15E5
4.01E-3
90
Y
64.1h
5.43E5
N/A
2.01E7
N/A
92
Y
3.54h
9.63E6
0.126 3.56E8
3.41E-5
93
Y
10.18h
3.31E6
0.11
1.23E8
2.98E-5
169
Yb
32.026d
2.41E4
1.219 8.93E5
3.30E-4
65
Zn
243.8d
8.24E3
3.575 3.05E5
9.68E-4
89
Zr
78.41h
4.50E5
5.65
1.66E7
1.53E-3
93
Zr
1.53E6y
2.52E-3 N/A
0.0931
N/A
95
Zr
64.02d
2.15E4
5.16
7.96E5
1.39E-3
97
Zr
16.91h
1.91E6
0.236 7.08E7
6.39E-5
The exposure rate from these radionuclides do not
include their short-lived progeny. Spontaneous fission,
isotopic m ixtures, im purities in m ixtures, and shielding
(including self shielding) should also be taken into
account when estim ating exposure rate.
44
Spontaneous Fission Neutron and Gamma Yields
mrem / hr
SF (years)
per Ci @ 30 cm
half-life
n/s/Ci
n/s/GBq neutron gamma
Es253
6.7E5
7.14E3
1.92E2
0.1
0.1
Cf252
85
2.64E9
7.14E7
2.93E4
1E4
Bk249
6E8
1.25E2
3.38
<0.1
<0.1
Cm244 1.38E7
1.11E5
3.0E3
1.2
0.4
Cm242 7.2E6
5.28E3
1.43E2
<0.1
0.1
Am241
2E14
0.18
4.86E-3
<0.1
<0.1
Pu242
7E10
4.56E5
1.23E4
5.0
2.0
Pu240
1.39E11
4.01E3
1.08E2
<0.1
0.1
Pu239
5.5E15
0.37
1.0E-2
<0.1
<0.1
Pu238
4.9E10
1.52E2
4.1
<0.1
<0.1
Pu236
3.5E9
69.7
1.88
<0.1
<0.1
Np237
1E18
0.18
4.86E-3
<0.1
<0.1
U 238
7E15
5.44E4
1.47E3
0.6
0.2
U235
1.9E17
3.15E2
8.51
<0.1
<0.1
U234
2E16
1.05
2.84E-2
<0.1
<0.1
U232
8E13
0.07
1.89E-3
<0.1
<0.1
Th232
1E21
1.18
3.19E-2
<0.1
<0.1
These neutron and gamma exposure rates are approximate
values for the spontaneous fission process. When you are
making exposure rate measurements you should take into
account shielding of the source (including self-shielding),
individual instrument response to both neutron and gamma
radiation, isotopic mixtures, age of the material (for both decay
and ingrowth), homogeneity of the material, and impurities.
Refer to the Specific Activity and Characteristic Radiations of
Commonly Encountered Radionuclides sections for information
on gamma exposure rates and radiations from primary decay
modes of these isotopes.
45
Spontaneous Fission Neutron and Gamma Yields
mrem / hr
SF (years)
per Ci @ 30 cm
half-life
n/s/Ci
n/s/GBq neutron gamma
Es253
6.7E5
7.14E3
1.92E2
0.1
0.1
Cf252
85
2.64E9
7.14E7
2.93E4
1E4
Bk249
6E8
1.25E2
3.38
<0.1
<0.1
Cm244 1.38E7
1.11E5
3.0E3
1.2
0.4
Cm242 7.2E6
5.28E3
1.43E2
<0.1
0.1
Am241
2E14
0.18
4.86E-3
<0.1
<0.1
Pu242
7E10
4.56E5
1.23E4
5.0
2.0
Pu240
1.39E11
4.01E3
1.08E2
<0.1
0.1
Pu239
5.5E15
0.37
1.0E-2
<0.1
<0.1
Pu238
4.9E10
1.52E2
4.1
<0.1
<0.1
Pu236
3.5E9
69.7
1.88
<0.1
<0.1
Np237
1E18
0.18
4.86E-3
<0.1
<0.1
U 238
7E15
5.44E4
1.47E3
0.6
0.2
U235
1.9E17
3.15E2
8.51
<0.1
<0.1
U234
2E16
1.05
2.84E-2
<0.1
<0.1
U232
8E13
0.07
1.89E-3
<0.1
<0.1
Th232
1E21
1.18
3.19E-2
<0.1
<0.1
These neutron and gamma exposure rates are approximate
values for the spontaneous fission process. When you are
making exposure rate measurements you should take into
account shielding of the source (including self-shielding),
individual instrument response to both neutron and gamma
radiation, isotopic mixtures, age of the material (for both decay
and ingrowth), homogeneity of the material, and impurities.
Refer to the Specific Activity and Characteristic Radiations of
Commonly Encountered Radionuclides sections for information
on gamma exposure rates and radiations from primary decay
modes of these isotopes.
45
Spontaneous Fission Neutron and Gamma Yields
mrem / hr
SF (years)
per Ci @ 30 cm
half-life
n/s/Ci
n/s/GBq neutron gamma
Es253
6.7E5
7.14E3
1.92E2
0.1
0.1
Cf 252
85
2.64E9
7.14E7
2.93E4
1E4
Bk249
6E8
1.25E2
3.38
<0.1
<0.1
Cm 244 1.38E7
1.11E5
3.0E3
1.2
0.4
Cm242 7.2E6
5.28E3
1.43E2
<0.1
0.1
Am241
2E14
0.18
4.86E-3
<0.1
<0.1
Pu242
7E10
4.56E5
1.23E4
5.0
2.0
Pu240
1.39E11
4.01E3
1.08E2
<0.1
0.1
Pu239
5.5E15
0.37
1.0E-2
<0.1
<0.1
Pu238
4.9E10
1.52E2
4.1
<0.1
<0.1
Pu236
3.5E9
69.7
1.88
<0.1
<0.1
Np237
1E18
0.18
4.86E-3
<0.1
<0.1
U 238
7E15
5.44E4
1.47E3
0.6
0.2
U235
1.9E17
3.15E2
8.51
<0.1
<0.1
U234
2E16
1.05
2.84E-2
<0.1
<0.1
U232
8E13
0.07
1.89E-3
<0.1
<0.1
Th232
1E21
1.18
3.19E-2
<0.1
<0.1
These neutron and gamma exposure rates are approximate
values for the spontaneous fission process. When you are
making exposure rate measurements you should take into
account shielding of the source (including self-shielding),
individual instrument response to both neutron and gamma
radiation, isotopic mixtures, age of the material (for both decay
and ingrowth), homogeneity of the material, and impurities.
Refer to the Specific Activity and Characteristic Radiations of
Commonly Encountered Radionuclides sections for information
on gamma exposure rates and radiations from primary decay
modes of these isotopes.
45
Spontaneous Fission Neutron and Gamma Yields
mrem / hr
SF (years)
per Ci @ 30 cm
half-life
n/s/Ci
n/s/GBq neutron gamma
Es253
6.7E5
7.14E3
1.92E2
0.1
0.1
Cf 252
85
2.64E9
7.14E7
2.93E4
1E4
Bk249
6E8
1.25E2
3.38
<0.1
<0.1
Cm244 1.38E7
1.11E5
3.0E3
1.2
0.4
Cm242 7.2E6
5.28E3
1.43E2
<0.1
0.1
Am241
2E14
0.18
4.86E-3
<0.1
<0.1
Pu242
7E10
4.56E5
1.23E4
5.0
2.0
Pu240
1.39E11
4.01E3
1.08E2
<0.1
0.1
Pu239
5.5E15
0.37
1.0E-2
<0.1
<0.1
Pu238
4.9E10
1.52E2
4.1
<0.1
<0.1
Pu236
3.5E9
69.7
1.88
<0.1
<0.1
Np237
1E18
0.18
4.86E-3
<0.1
<0.1
U238
7E15
5.44E4
1.47E3
0.6
0.2
U235
1.9E17
3.15E2
8.51
<0.1
<0.1
U234
2E16
1.05
2.84E-2
<0.1
<0.1
U232
8E13
0.07
1.89E-3
<0.1
<0.1
Th232
1E21
1.18
3.19E-2
<0.1
<0.1
These neutron and gamma exposure rates are approximate
values for the spontaneous fission process. When you are
making exposure rate measurements you should take into
account shielding of the source (including self-shielding),
individual instrument response to both neutron and gamma
radiation, isotopic mixtures, age of the material (for both decay
and ingrowth), homogeneity of the material, and impurities.
Refer to the Specific Activity and Characteristic Radiations of
Commonly Encountered Radionuclides sections for information
on gamma exposure rates and radiations from primary decay
modes of these isotopes.
45
Energy & Yield of neutrons from the alpha, n reaction
neutron
ç energy
mrem/hr per Ci
MeV
n/s/GBq
n/s/Ci
@ 30 cm
Cf252O
4.5
8.73E6
3.23E8
3,600
Cm244Be
4
1.0E5
3.7E6
41.1
Cm244O
1.9
1.0E5
3.7E6
41.1
Cm242Be
4
1.12E5
4.1E6
45.5
Cm242O
1.9
1.12E5
4.1E6
45.5
Am241Be
4.5
7.6E4
2.8E6
34.7
Am241B
2.8
1.3E4
4.8E5
5.9
Am241F
1.3
4.1E3
1.5E4
0.17
Am241Li
0.7
1.4E3
5.2E4
0.29
Am241O
1.9
250
9.23E3
0.1
Pu242O
1.7
2.13E-4
7.88E-3
8.7E-8
Pu240O
1.9
0.86
32
3.6E-4
Pu239Be
4.5
6.1E4
2.3E6
28.5
Pu239O
1.9
0.06
2.36
2.6E-5
Pu238Be
4.5
7.9E4
2.9E6
32.2
Pu238O
1.9
6.19E3
2.29E5
2.5
Pu239F
1.4
5.4E3
2E5
2.2
Pu238Li
0.6
38
1.4E3
0.008
Pu238C13
3.6
1.1E4
4.1E4
0.46
Pu236O
2.0
54
2E3
0.02
Np237O
1.2
54
2E3
0.02
U238O, U235O, U234O, U233O, and U232O have similar alpha
particle energies, therefore the energy and yield of the neutrons
from the uranium oxide alpha, n reactions are similar.
1.2
54
2E3
0.02
Th232O
1.2
54
2E3
0.02
46
Energy & Yield of neutrons from the alpha, n reaction
neutron
ç energy
mrem/hr per Ci
MeV
n/s/GBq
n/s/Ci
@ 30 cm
Cf252O
4.5
8.73E6
3.23E8
3,600
Cm244Be
4
1.0E5
3.7E6
41.1
Cm244O
1.9
1.0E5
3.7E6
41.1
Cm242Be
4
1.12E5
4.1E6
45.5
Cm242O
1.9
1.12E5
4.1E6
45.5
Am241Be
4.5
7.6E4
2.8E6
34.7
Am241B
2.8
1.3E4
4.8E5
5.9
Am241F
1.3
4.1E3
1.5E4
0.17
Am241Li
0.7
1.4E3
5.2E4
0.29
Am241O
1.9
250
9.23E3
0.1
Pu242O
1.7
2.13E-4
7.88E-3
8.7E-8
Pu240O
1.9
0.86
32
3.6E-4
Pu239Be
4.5
6.1E4
2.3E6
28.5
Pu239O
1.9
0.06
2.36
2.6E-5
Pu238Be
4.5
7.9E4
2.9E6
32.2
Pu238O
1.9
6.19E3
2.29E5
2.5
Pu239F
1.4
5.4E3
2E5
2.2
Pu238Li
0.6
38
1.4E3
0.008
Pu238C13
3.6
1.1E4
4.1E4
0.46
Pu236O
2.0
54
2E3
0.02
Np237O
1.2
54
2E3
0.02
U238O, U235O, U234O, U233O, and U232O have similar alpha
particle energies, therefore the energy and yield of the neutrons
from the uranium oxide alpha, n reactions are similar.
1.2
54
2E3
0.02
Th232O
1.2
54
2E3
0.02
46
Energy & Yield of neutrons from the alpha, n reaction
neutron
ç energy
mrem/hr per Ci
MeV
n/s/GBq
n/s/Ci
@ 30 cm
Cf252O
4.5
8.73E6
3.23E8
3,600
Cm244Be
4
1.0E5
3.7E6
41.1
Cm244O
1.9
1.0E5
3.7E6
41.1
Cm242Be
4
1.12E5
4.1E6
45.5
Cm242O
1.9
1.12E5
4.1E6
45.5
Am241Be
4.5
7.6E4
2.8E6
34.7
Am241B
2.8
1.3E4
4.8E5
5.9
Am241F
1.3
4.1E3
1.5E4
0.17
Am241Li
0.7
1.4E3
5.2E4
0.29
Am241O
1.9
250
9.23E3
0.1
Pu242O
1.7
2.13E-4
7.88E-3
8.7E-8
Pu240O
1.9
0.86
32
3.6E-4
Pu239Be
4.5
6.1E4
2.3E6
28.5
Pu239O
1.9
0.06
2.36
2.6E-5
Pu238Be
4.5
7.9E4
2.9E6
32.2
Pu238O
1.9
6.19E3
2.29E5
2.5
Pu239F
1.4
5.4E3
2E5
2.2
Pu238Li
0.6
38
1.4E3
0.008
Pu238C13
3.6
1.1E4
4.1E4
0.46
Pu236O
2.0
54
2E3
0.02
Np237O
1.2
54
2E3
0.02
U238 O, U235O, U234O, U233O, and U232 O have similar alpha
particle energies, therefore the energy and yield of the neutrons
from the uranium oxide alpha, n reactions are similar.
1.2
54
2E3
0.02
Th232O
1.2
54
2E3
0.02
46
Energy & Yield of neutrons from the alpha, n reaction
neutron
ç energy
mrem/hr per Ci
MeV
n/s/GBq
n/s/Ci
@ 30 cm
Cf252O
4.5
8.73E6
3.23E8
3,600
Cm244Be
4
1.0E5
3.7E6
41.1
Cm244O
1.9
1.0E5
3.7E6
41.1
Cm242Be
4
1.12E5
4.1E6
45.5
Cm242O
1.9
1.12E5
4.1E6
45.5
Am241Be
4.5
7.6E4
2.8E6
34.7
Am241B
2.8
1.3E4
4.8E5
5.9
Am241F
1.3
4.1E3
1.5E4
0.17
Am241Li
0.7
1.4E3
5.2E4
0.29
Am241O
1.9
250
9.23E3
0.1
Pu242O
1.7
2.13E-4
7.88E-3
8.7E-8
Pu240O
1.9
0.86
32
3.6E-4
Pu239Be
4.5
6.1E4
2.3E6
28.5
Pu239O
1.9
0.06
2.36
2.6E-5
Pu238Be
4.5
7.9E4
2.9E6
32.2
Pu238O
1.9
6.19E3
2.29E5
2.5
Pu239F
1.4
5.4E3
2E5
2.2
Pu238Li
0.6
38
1.4E3
0.008
Pu238C13
3.6
1.1E4
4.1E4
0.46
Pu236O
2.0
54
2E3
0.02
Np237O
1.2
54
2E3
0.02
U238 O, U235O, U234O, U233O, and U232 O have similar alpha
particle energies, therefore the energy and yield of the neutrons
from the uranium oxide alpha, n reactions are similar.
1.2
54
2E3
0.02
Th232O
1.2
54
2E3
0.02
46
Energy & Yield of neutrons from the alpha, n reaction
neutron
ç energy
mrem/hr per Ci
MeV
n/s/GBq
n/s/Ci
@ 30 cm
Ac227Be
Ra226Be
Ra226B
Po210Be
Po210Li
Po210B
Po210F
av 5
av 4.5
3.0
4.2
0.48
2.5
0.42
7.02E5
5.02E5
8.0E4
7.1E4
1.2E3
1.0E3
3E3
2.6E7
1.9E7
3.0E5
2.6E6
4.4E4
3.7E5
1.1E5
Energy & Yield of neutrons from the alpha, n reaction
neutron
ç energy
mrem/hr per Ci
MeV
n/s/GBq
n/s/Ci
@ 30 cm
Ac227Be
Ra226Be
Ra226B
Po210Be
Po210Li
Po210B
Po210F
289
211
3.3
28.9
0.49
4.1
1.2
Ra226 and Ac227 include progeny effects
ç energy (MeV)
0.3
4.2
2.9
4.4
1.9
1.2
?
2.7
1.0
1.2
?
47
av 5
av 4.5
3.0
4.2
0.48
2.5
0.42
7.02E5
5.02E5
8.0E4
7.1E4
1.2E3
1.0E3
3E3
n/s/GBq
1.13E3
6.5E4
1.75E4
7.8E1
5.9E1
5.9E3
1.1E3
8.9E2
4.1E2
7.6E1
7E1
n/s/Ci
4.2E4
2.4E6
6.5E5
2.9E3
2.2E3
2.2E5
4.1E4
3.3E4
1.5E4
2.8E3
2.6E3
2.6E7
1.9E7
3.0E5
2.6E6
4.4E4
3.7E5
1.1E5
á, ç sources
Li
Be
B
C
O
F
Na
Mg
Al
Si
Cl
ç energy (MeV)
0.3
4.2
2.9
4.4
1.9
1.2
?
2.7
1.0
1.2
?
47
n/s/GBq
1.13E3
6.5E4
1.75E4
7.8E1
5.9E1
5.9E3
1.1E3
8.9E2
4.1E2
7.6E1
7E1
n/s/Ci
4.2E4
2.4E6
6.5E5
2.9E3
2.2E3
2.2E5
4.1E4
3.3E4
1.5E4
2.8E3
2.6E3
av 5
av 4.5
3.0
4.2
0.48
2.5
0.42
7.02E5
5.02E5
8.0E4
7.1E4
1.2E3
1.0E3
3E3
2.6E7
1.9E7
3.0E5
2.6E6
4.4E4
3.7E5
1.1E5
289
211
3.3
28.9
0.49
4.1
1.2
Ra226 and Ac227 include progeny effects
Energy & Yield for 5.2 MeV
alpha particles for various elements
ç energy (MeV)
0.3
4.2
2.9
4.4
1.9
1.2
?
2.7
1.0
1.2
?
47
289
211
3.3
28.9
0.49
4.1
1.2
Energy & Yield of neutrons from the alpha, n reaction
neutron
ç energy
mrem/hr per Ci
MeV
n/s/GBq
n/s/Ci
@ 30 cm
Ac227Be
Ra226Be
Ra226B
Po210Be
Po210Li
Po210B
Po210F
289
211
3.3
28.9
0.49
4.1
1.2
Ra226 and Ac227 include progeny effects
á, ç sources
Li
Be
B
C
O
F
Na
Mg
Al
Si
Cl
2.6E7
1.9E7
3.0E5
2.6E6
4.4E4
3.7E5
1.1E5
Energy & Yield for 5.2 MeV
alpha particles for various elements
Energy & Yield of neutrons from the alpha, n reaction
neutron
ç energy
mrem/hr per Ci
MeV
n/s/GBq
n/s/Ci
@ 30 cm
Ac227Be
Ra226Be
Ra226B
Po210Be
Po210Li
Po210B
Po210F
7.02E5
5.02E5
8.0E4
7.1E4
1.2E3
1.0E3
3E3
Ra226 and Ac227 include progeny effects
Energy & Yield for 5.2 MeV
alpha particles for various elements
á, ç sources
Li
Be
B
C
O
F
Na
Mg
Al
Si
Cl
av 5
av 4.5
3.0
4.2
0.48
2.5
0.42
n/s/GBq
1.13E3
6.5E4
1.75E4
7.8E1
5.9E1
5.9E3
1.1E3
8.9E2
4.1E2
7.6E1
7E1
Energy & Yield for 5.2 MeV
alpha particles for various elements
n/s/Ci
4.2E4
2.4E6
6.5E5
2.9E3
2.2E3
2.2E5
4.1E4
3.3E4
1.5E4
2.8E3
2.6E3
á, ç sources
Li
Be
B
C
O
F
Na
Mg
Al
Si
Cl
ç energy (MeV)
0.3
4.2
2.9
4.4
1.9
1.2
?
2.7
1.0
1.2
?
47
n/s/GBq
1.13E3
6.5E4
1.75E4
7.8E1
5.9E1
5.9E3
1.1E3
8.9E2
4.1E2
7.6E1
7E1
n/s/Ci
4.2E4
2.4E6
6.5E5
2.9E3
2.2E3
2.2E5
4.1E4
3.3E4
1.5E4
2.8E3
2.6E3
CHARACTERISTIC RADIATIONS OF
COMMONLY ENCOUNTERED RADIONUCLIDES
These tables show the type of radiation, its energy in keV, its
half-life, the half-life of its first progeny, and the % abundance
of that energy for the parent. Only the most abundant
energies are listed. 'S' indicates the isotope is stable.
1st
Radiation
Progeny
type kev and % abundance
3
3
H
He
â
18.6 (100)
12.32y
S
7
Be
53.44d
Li
S
14
N
S
15
N
S
16
O
S
C
5,730y
O
122.24s
N
7.13s
7
EC
ã
14
15
16
18
18
F
O
109.74m S
Na
2.602y
22
Ne
S
24
Mg
S
Na
15.00h
22
24
7
478 (10.42)
7
Li
S
14
N
S
15
N
S
16
O
S
C
5,730y
O
122.24s
N
7.13s
18
7
15
16
18
F
O
109.74m S
Na
2.602y
22
Ne
S
24
Mg
S
Na
15.00h
22
24
7
Li
S
157 (100)
C
5,730y
+
1732 (99.9)
511 (200)
O
122.24s
-
3302 (4.9), 4288 (68), 10418 (26)
6129 (69), 7115 (5)
N
7.13s
+
634 (96.73)
511 (194)
F
O
109.74m S
â
ã
â
ã
â
ã
+
â
546 (89.84)
ã
1275 (99.94)
Ne x-rays 1 (0.12)
â
ã
-
EC
ã
14
Be
53.44d
-
â
1390 (99.935)
1369 (99.9991), 2754 (99.862)
CHARACTERISTIC RADIATIONS OF
COMMONLY ENCOUNTERED RADIONUCLIDES
These tables show the type of radiation, its energy in keV, its
half-life, the half-life of its first progeny, and the % abundance
of that energy for the parent. Only the most abundant
energies are listed. 'S' indicates the isotope is stable.
1st
Radiation
Progeny
type kev and % abundance
3
3
H
He
â
18.6 (100)
12.32y
S
Be
53.44d
CHARACTERISTIC RADIATIONS OF
COMMONLY ENCOUNTERED RADIONUCLIDES
These tables show the type of radiation, its energy in keV, its
half-life, the half-life of its first progeny, and the % abundance
of that energy for the parent. Only the most abundant
energies are listed. 'S' indicates the isotope is stable.
1st
Radiation
Progeny
type kev and % abundance
3
3
H
He
â
18.6 (100)
12.32y
S
14
N
S
15
N
S
16
O
S
14
15
16
18
18
Na
2.602y
22
Ne
S
24
Mg
S
Na
15.00h
Be
53.44d
14
N
S
15
N
S
16
O
S
C
5,730y
+
1732 (99.9)
511 (200)
O
122.24s
-
3302 (4.9), 4288 (68), 10418 (26)
6129 (69), 7115 (5)
N
7.13s
+
634 (96.73)
511 (194)
F
O
109.74m S
â
ã
â
ã
+
â
546 (89.84)
ã
1275 (99.94)
Ne x-rays 1 (0.12)
â
ã
-
1390 (99.935)
1369 (99.9991), 2754 (99.862)
-
157 (100)
+
1732 (99.9)
511 (200)
-
3302 (4.9), 4288 (68), 10418 (26)
6129 (69), 7115 (5)
+
634 (96.73)
511 (194)
â
â
ã
â
ã
â
ã
+
â
546 (89.84)
ã
1275 (99.94)
Ne x-rays 1 (0.12)
â
ã
-
18
EC
ã
14
157 (100)
â
ã
24
7
Li
S
-
â
22
478 (10.42)
1390 (99.935)
1369 (99.9991), 2754 (99.862)
CHARACTERISTIC RADIATIONS OF
COMMONLY ENCOUNTERED RADIONUCLIDES
These tables show the type of radiation, its energy in keV, its
half-life, the half-life of its first progeny, and the % abundance
of that energy for the parent. Only the most abundant
energies are listed. 'S' indicates the isotope is stable.
1st
Radiation
Progeny
type kev and % abundance
3
3
H
He
â
18.6 (100)
12.32y
S
7
478 (10.42)
EC
ã
15
16
18
Na
2.602y
22
Ne
S
24
Mg
S
Na
15.00h
22
24
478 (10.42)
-
157 (100)
+
1732 (99.9)
511 (200)
-
3302 (4.9), 4288 (68), 10418 (26)
6129 (69), 7115 (5)
+
634 (96.73)
511 (194)
â
â
ã
â
ã
â
ã
+
â
546 (89.84)
ã
1275 (99.94)
Ne x-rays 1 (0.12)
â
ã
-
1390 (99.935)
1369 (99.9991), 2754 (99.862)
26
Al
7.17E5
32
P
14.29d
36
Cl
3.01E5y
40
K
1.27E9y
41
Ar
1.827h
26
Mg
S
32
S
87.2d
36
Ar
S
40
Ca
S
40
Ar
S
41
K
S
42
Ca
S
42
43
Ca
S
43
K
12.36h
K
22.6h
Sc
83.83d
46
Ti
S
46
47
Ti
S
47
Sc
3.351d
+
â
1174 ((81.81)
ã 130 (2.5), 1809 (99.96), 2938 (0.24)
Mg x-rays 1 (0.44)
26
Al
7.17E5
-
1710 (100)
P
14.29d
-
710 (99.0)
Cl
3.01E5y
-
1312 (89.33)
K
1.27E9y
â
â
â
EC
ã
1461 (10.67)
Ar x-rays 3 (0.94)
-
â
ã
1198 (99.17), 2492 (0.78)
1294 (99.16)
-
â 1684 (0.32), 1996 (17.5), 3521 (82.1)
ã
313 (0.319), 1525 (17.9)
-
â
ã
36
40
41
Ar
1.827h
32
S
87.2d
Ar
S
36
40
Ca
S
40
Ar
S
41
K
S
42
Ca
S
42
43
Ca
S
43
K
12.36h
422 (2.24), 827 (92.2), 1224 (3.6)
373 (87.3), 397 (11.43), 593 (11.0),
617 (80.5)
K
22.6h
-
357 (99.996)
889 (99.983), 1121 (99.987)
Sc
83.83d
46
Ti
S
46
-
441 (68), 601 (32)
159 (68)
Sc
3.351d
47
Ti
S
47
â
ã
â
ã
32
26
Mg
S
+
â
1174 ((81.81)
ã 130 (2.5), 1809 (99.96), 2938 (0.24)
Mg x-rays 1 (0.44)
-
1710 (100)
-
710 (99.0)
-
1312 (89.33)
â
â
â
EC
ã
1461 (10.67)
Ar x-rays 3 (0.94)
-
â
ã
-
â 1684 (0.32), 1996 (17.5), 3521 (82.1)
ã
313 (0.319), 1525 (17.9)
â
ã
-
26
32
P
14.29d
36
Cl
3.01E5y
40
K
1.27E9y
41
Ar
1.827h
26
Mg
S
32
S
87.2d
36
Ar
S
40
Ca
S
40
Ar
S
41
K
S
42
Ca
S
42
43
Ca
S
43
K
12.36h
K
22.6h
Sc
83.83d
46
Ti
S
46
47
Ti
S
47
Sc
3.351d
+
â
1174 ((81.81)
ã 130 (2.5), 1809 (99.96), 2938 (0.24)
Mg x-rays 1 (0.44)
357 (99.996)
889 (99.983), 1121 (99.987)
-
441 (68), 601 (32)
159 (68)
â
ã
49
26
Al
7.17E5
32
-
1710 (100)
P
14.29d
-
710 (99.0)
Cl
3.01E5y
-
1312 (89.33)
K
1.27E9y
â
â
â
EC
ã
1461 (10.67)
Ar x-rays 3 (0.94)
-
â
ã
1198 (99.17), 2492 (0.78)
1294 (99.16)
-
â 1684 (0.32), 1996 (17.5), 3521 (82.1)
ã
313 (0.319), 1525 (17.9)
-
â
ã
â
ã
36
40
41
Ar
1.827h
26
Mg
S
32
S
87.2d
Ar
S
36
40
Ca
S
40
Ar
S
41
K
S
42
Ca
S
42
43
Ca
S
43
K
12.36h
422 (2.24), 827 (92.2), 1224 (3.6)
373 (87.3), 397 (11.43), 593 (11.0),
617 (80.5)
K
22.6h
-
357 (99.996)
889 (99.983), 1121 (99.987)
Sc
83.83d
46
Ti
S
46
-
441 (68), 601 (32)
159 (68)
Sc
3.351d
47
Ti
S
47
â
ã
49
422 (2.24), 827 (92.2), 1224 (3.6)
373 (87.3), 397 (11.43), 593 (11.0),
617 (80.5)
-
â
ã
49
Al
7.17E5
1198 (99.17), 2492 (0.78)
1294 (99.16)
+
â
1174 ((81.81)
ã 130 (2.5), 1809 (99.96), 2938 (0.24)
Mg x-rays 1 (0.44)
-
1710 (100)
-
710 (99.0)
-
1312 (89.33)
â
â
â
EC
ã
1461 (10.67)
Ar x-rays 3 (0.94)
-
â
ã
1198 (99.17), 2492 (0.78)
1294 (99.16)
-
â 1684 (0.32), 1996 (17.5), 3521 (82.1)
ã
313 (0.319), 1525 (17.9)
â
ã
-
422 (2.24), 827 (92.2), 1224 (3.6)
373 (87.3), 397 (11.43), 593 (11.0),
617 (80.5)
-
357 (99.996)
889 (99.983), 1121 (99.987)
-
441 (68), 601 (32)
159 (68)
â
ã
â
ã
49
48
Sc
43.7h
48
V
16.238d
51
Ti
S
48
Ti
S
48
â
697 (50.1)
ã
944 (7.76), 984 (100), 1312 (97.5)
Ti x-rays 0.45 (0.15), 5 (9.74)
V
16.238d
51
EC
ã
320 (9.83)
V x-rays 1 (0.33), 5 (22.31)
Cr
27.704d
V
S
52
Cr
S
Cr
27.704d
V
S
52
Cr
S
Mn
312.5d
54
Cr
S
55
Mn
S
Mn
2.5789h
56
Fe
S
56
Fe
S
Mn
5.591d
Fe
2.7y
Co
78.76d
52
54
55
56
56
â
ã
-
482 (10.01), 657 (89.99)
984 (100), 1037 (97.5), 1312 (100)
+
+
Sc
43.7h
48
Ti
S
48
48
Ti
S
48
â
697 (50.1)
ã
944 (7.76), 984 (100), 1312 (97.5)
Ti x-rays 0.45 (0.15), 5 (9.74)
51
EC
ã
320 (9.83)
V x-rays 1 (0.33), 5 (22.31)
51
52
â
ã
575 (29.4)
511 (67), 744 (82), 935 (84),
1434 (100)
Cr x-rays 1 (0.26), 5 (15.5), 6 (2.06)
Mn
5.591d
EC
ã
835 (99.975)
Cr x-rays 1 (0.37), 5 (22.13), 6 (2.94)
Mn
312.5d
54
Cr
S
EC
Mn x-rays 1 (0.42), 6 (24.5), 6 (3.29)
Fe
2.7y
55
Mn
S
Mn
2.5789h
56
Fe
S
56
Fe
S
-
â
ã
736 (14.6), 1038 (27.8), 2849 (56.2)
847 (98.9), 1811 (27.2), 2113 (14.3)
+
â
423 (1.05), 1461 (18.7)
ã 847 (99.958), 1038 (14.03),
1238 (67.0), 1771 (15.5), 2598 (16.9)
Fe x-rays 1 (0.34), 6 (21.83), 7 (2.92)
Co
78.76d
54
55
56
56
-
â
ã
+
+
575 (29.4)
511 (67), 744 (82), 935 (84),
1434 (100)
Cr x-rays 1 (0.26), 5 (15.5), 6 (2.06)
â
ã
EC
ã
835 (99.975)
Cr x-rays 1 (0.37), 5 (22.13), 6 (2.94)
EC
Mn x-rays 1 (0.42), 6 (24.5), 6 (3.29)
-
â
ã
48
+
48
V
16.238d
51
48
48
Ti
S
48
â
697 (50.1)
ã
944 (7.76), 984 (100), 1312 (97.5)
Ti x-rays 0.45 (0.15), 5 (9.74)
51
EC
ã
320 (9.83)
V x-rays 1 (0.33), 5 (22.31)
â
697 (50.1)
ã
944 (7.76), 984 (100), 1312 (97.5)
Ti x-rays 0.45 (0.15), 5 (9.74)
V
16.238d
51
EC
ã
320 (9.83)
V x-rays 1 (0.33), 5 (22.31)
Cr
27.704d
V
S
52
Cr
S
Cr
S
Mn
312.5d
54
Cr
S
55
Mn
S
Mn
2.5789h
56
Fe
S
56
Fe
S
Co
78.76d
Ti
S
48
52
Fe
2.7y
48
Ti
S
V
S
Mn
5.591d
Sc
43.7h
48
Cr
27.704d
52
54
55
56
56
-
50
Ti
S
â
ã
482 (10.01), 657 (89.99)
984 (100), 1037 (97.5), 1312 (100)
+
+
51
52
â
ã
575 (29.4)
511 (67), 744 (82), 935 (84),
1434 (100)
Cr x-rays 1 (0.26), 5 (15.5), 6 (2.06)
Mn
5.591d
EC
ã
835 (99.975)
Cr x-rays 1 (0.37), 5 (22.13), 6 (2.94)
Mn
312.5d
54
Cr
S
EC
Mn x-rays 1 (0.42), 6 (24.5), 6 (3.29)
Fe
2.7y
55
Mn
S
Mn
2.5789h
56
Fe
S
56
Fe
S
-
â
ã
736 (14.6), 1038 (27.8), 2849 (56.2)
847 (98.9), 1811 (27.2), 2113 (14.3)
+
â
423 (1.05), 1461 (18.7)
ã 847 (99.958), 1038 (14.03),
1238 (67.0), 1771 (15.5), 2598 (16.9)
Fe x-rays 1 (0.34), 6 (21.83), 7 (2.92)
50
736 (14.6), 1038 (27.8), 2849 (56.2)
847 (98.9), 1811 (27.2), 2113 (14.3)
â
423 (1.05), 1461 (18.7)
ã 847 (99.958), 1038 (14.03),
1238 (67.0), 1771 (15.5), 2598 (16.9)
Fe x-rays 1 (0.34), 6 (21.83), 7 (2.92)
50
Sc
43.7h
482 (10.01), 657 (89.99)
984 (100), 1037 (97.5), 1312 (100)
Co
78.76d
54
55
56
56
-
â
ã
482 (10.01), 657 (89.99)
984 (100), 1037 (97.5), 1312 (100)
+
+
575 (29.4)
511 (67), 744 (82), 935 (84),
1434 (100)
Cr x-rays 1 (0.26), 5 (15.5), 6 (2.06)
â
ã
EC
ã
835 (99.975)
Cr x-rays 1 (0.37), 5 (22.13), 6 (2.94)
EC
Mn x-rays 1 (0.42), 6 (24.5), 6 (3.29)
-
â
ã
736 (14.6), 1038 (27.8), 2849 (56.2)
847 (98.9), 1811 (27.2), 2113 (14.3)
+
â
423 (1.05), 1461 (18.7)
ã 847 (99.958), 1038 (14.03),
1238 (67.0), 1771 (15.5), 2598 (16.9)
Fe x-rays 1 (0.34), 6 (21.83), 7 (2.92)
50
57
Ni
35.60h
57
Co
270.9d
Co
270.9d
57
Fe
S
57
Co
70.8d
58
Fe
S
Ni
7.5E4y
59
+
â
463 (0.87), 716 (5.7), 843 (33.1)
ã
127 (12.9), 1378 (77.9), 1919(14.7)
Co x-rays 1 (0.29), 7 (18.1), 8 (2.46)
EC
ã
14 (9.54), 122 (85.51), 136 (10.6)
Fe x-rays 1 (0.8), 6 (49.4), 7 (6.62)
57
Co
270.9d
Co
270.9d
57
Fe
S
58
57
58
â
475 (14.93)
ã
811 (99.4), 864 (0.74), 1675 (0.54)
Fe x-rays 0.7 (0.36), 6 (23.18), 7 (3.1)
Co
70.8d
Fe
S
Co
S
59
EC
Co x-rays 1 (0.47), 7 (29.8)
Ni
7.5E4y
59
Fe
44.53d
59
Co
S
59
Co
5.271y
60
Ni
S
60
Cu
9.673m
62
Ni
S
62
65
Cu
S
65
Cu
S
65
Zn
243.66d
65
Ni
2.520h
+
57
Ni
35.60h
-
â
ã
-
â
ã
131 (1.37), 273 (45.2), 466 (53.1)
192 (3.11), 1099 (56.5), 1292 (43.2)
318 (100)
1173 (100), 1332 (100)
+
58
â
475 (14.93)
ã
811 (99.4), 864 (0.74), 1675 (0.54)
Fe x-rays 0.7 (0.36), 6 (23.18), 7 (3.1)
Co
S
59
EC
Co x-rays 1 (0.47), 7 (29.8)
Fe
44.53d
59
Co
S
59
Co
5.271y
60
Ni
S
60
62
â
1754 (0.132), 2927 (97.59)
ã
876 (0.148), 1173 (0.336)
Ni x-rays 7 (0.7)
Cu
9.673m
62
Ni
S
EC
+
â
330 (1.415)
ã
1116 (50.75)
Cu x-rays 1 (0.57), 8 (34.1), 9 (4.61)
Zn
243.66d
65
Cu
S
65
Cu
S
65
-
â
ã
2130 (100)
368 (4.5), 1115 (16), 1481 (25)
+
â
463 (0.87), 716 (5.7), 843 (33.1)
ã
127 (12.9), 1378 (77.9), 1919(14.7)
Co x-rays 1 (0.29), 7 (18.1), 8 (2.46)
EC
ã
14 (9.54), 122 (85.51), 136 (10.6)
Fe x-rays 1 (0.8), 6 (49.4), 7 (6.62)
65
Ni
2.520h
+
â
ã
â
ã
-
-
57
57
Co
270.9d
Co
270.9d
57
Fe
S
57
Co
70.8d
58
Fe
S
Ni
7.5E4y
59
+
â
463 (0.87), 716 (5.7), 843 (33.1)
ã
127 (12.9), 1378 (77.9), 1919(14.7)
Co x-rays 1 (0.29), 7 (18.1), 8 (2.46)
EC
ã
14 (9.54), 122 (85.51), 136 (10.6)
Fe x-rays 1 (0.8), 6 (49.4), 7 (6.62)
+
EC
+
â
330 (1.415)
ã
1116 (50.75)
Cu x-rays 1 (0.57), 8 (34.1), 9 (4.61)
-
â
ã
57
Ni
35.60h
57
Co
270.9d
Co
270.9d
57
Fe
S
58
57
â
475 (14.93)
ã
811 (99.4), 864 (0.74), 1675 (0.54)
Fe x-rays 0.7 (0.36), 6 (23.18), 7 (3.1)
Co
S
59
EC
Co x-rays 1 (0.47), 7 (29.8)
Fe
44.53d
59
Co
S
59
Co
5.271y
60
Ni
S
60
62
Co
70.8d
Fe
S
Co
S
59
EC
Co x-rays 1 (0.47), 7 (29.8)
Ni
7.5E4y
59
Fe
44.53d
59
Co
S
59
Co
5.271y
60
Ni
S
60
Cu
9.673m
62
Ni
S
62
65
Cu
S
65
Cu
S
65
65
Ni
2.520h
-
-
â
ã
131 (1.37), 273 (45.2), 466 (53.1)
192 (3.11), 1099 (56.5), 1292 (43.2)
318 (100)
1173 (100), 1332 (100)
â
1754 (0.132), 2927 (97.59)
ã
876 (0.148), 1173 (0.336)
Ni x-rays 7 (0.7)
Cu
9.673m
62
Ni
S
EC
+
â
330 (1.415)
ã
1116 (50.75)
Cu x-rays 1 (0.57), 8 (34.1), 9 (4.61)
Zn
243.66d
65
Cu
S
65
Cu
S
65
+
-
â
ã
2130 (100)
368 (4.5), 1115 (16), 1481 (25)
51
+
â
463 (0.87), 716 (5.7), 843 (33.1)
ã
127 (12.9), 1378 (77.9), 1919(14.7)
Co x-rays 1 (0.29), 7 (18.1), 8 (2.46)
EC
ã
14 (9.54), 122 (85.51), 136 (10.6)
Fe x-rays 1 (0.8), 6 (49.4), 7 (6.62)
58
â
475 (14.93)
ã
811 (99.4), 864 (0.74), 1675 (0.54)
Fe x-rays 0.7 (0.36), 6 (23.18), 7 (3.1)
â
ã
2130 (100)
368 (4.5), 1115 (16), 1481 (25)
51
58
Zn
243.66d
+
318 (100)
1173 (100), 1332 (100)
â
1754 (0.132), 2927 (97.59)
ã
876 (0.148), 1173 (0.336)
Ni x-rays 7 (0.7)
51
Ni
35.60h
131 (1.37), 273 (45.2), 466 (53.1)
192 (3.11), 1099 (56.5), 1292 (43.2)
65
Ni
2.520h
+
â
ã
â
ã
-
-
131 (1.37), 273 (45.2), 466 (53.1)
192 (3.11), 1099 (56.5), 1292 (43.2)
318 (100)
1173 (100), 1332 (100)
+
â
1754 (0.132), 2927 (97.59)
ã
876 (0.148), 1173 (0.336)
Ni x-rays 7 (0.7)
EC
+
â
330 (1.415)
ã
1116 (50.75)
Cu x-rays 1 (0.57), 8 (34.1), 9 (4.61)
-
â
ã
2130 (100)
368 (4.5), 1115 (16), 1481 (25)
51
68
Ga
67.7m
68
Zn
S
As
17.77d
74
Se75
119.78d
Ge
270.9d
68
Ga
67.7m
85
Kr
10.72y
68
EC
Ga x-rays 1 (0.67), 9 (38.7), 10 (5.46)
+
â
822 (0.012), 1899 (0.8794)
ã
1077 (0.032), 1883 (0.0014)
Zn x-rays 9 (0.049), 10 (0.00579
Se
S
74
Ge
S
74
â
1353 (34.0)
ã
634 (15.4)
EC
+
â
1540 (66.0)
ã 596 (59.9), 608 (0.55), 1204 (0.287)
Ge x-rays 1 (0.26), 10 (15), 11 (2.22)
As75
S
EC
ã
136 (59.2), 265 (59.8), 280 (25.2)
As x-rays 1 (0.9), 11 (47.5), 12 (7.3)
Rb
S
88
85
88
Rb
Sr
17.772m S
89
Rb
15.15m
89
Sr
50.53m
89
Y
S
Sr
28.9y
90
Y
64.00h
90
Y
64.00h
90
Zr
S
68
Ga
67.7m
68
Zn
S
74
Se
S
74
Ge
S
75
As
S
Sr
50.53m
Ge
270.9d
68
Ga
67.7m
As
17.77d
Se
119.78d
85
Kr
10.72y
89
90
89
Se75
119.78d
89
90
Y
64.00h
90
Zr
S
90
â
1353 (34.0)
ã
634 (15.4)
EC
+
â
1540 (66.0)
ã 596 (59.9), 608 (0.55), 1204 (0.287)
Ge x-rays 1 (0.26), 10 (15), 11 (2.22)
As75
S
EC
ã
136 (59.2), 265 (59.8), 280 (25.2)
As x-rays 1 (0.9), 11 (47.5), 12 (7.3)
2581 (13.3), 3479 (4.1), 5315 (78)
898 (14), 1836 (21.4), 2678 (1.96)
Rb
Sr
17.772m S
-
1275 (33), 2223 (34), 4503 (25)
1031 (58), 1248 (42), 2196 (13.3)
Rb
15.15m
-
1491 (99.985)
av. 909 (0.02%)
Sr
50.53m
-
546 (100)
-
519 (0.0115), 2284 (99.9885)
â
ã
â
ã
â
â
-
Rb
S
88
89
89
Y
S
Sr
28.9y
90
Y
64.00h
90
Y
64.00h
90
Zr
S
68
Ga
67.7m
68
Zn
S
74
Se
S
74
Ge
S
75
As
S
Ge
270.9d
68
Ga
67.7m
90
Kr
10.72y
-
2581 (13.3), 3479 (4.1), 5315 (78)
898 (14), 1836 (21.4), 2678 (1.96)
Rb
Sr
17.772m S
-
1275 (33), 2223 (34), 4503 (25)
1031 (58), 1248 (42), 2196 (13.3)
Rb
15.15m
-
1491 (99.985)
av. 909 (0.02%)
Sr
50.53m
-
546 (100)
-
519 (0.0115), 2284 (99.9885)
Sr
28.9y
90
Y
64.00h
â
ã
â
ã
â
â
85
89
173 (0.437), 687 (99.563)
514 (0.434)
â
ã
88
Sr
50.53m
-
â
ã
85
89
Se
119.78d
89
74
-
â
ã
85
EC
ã
136 (59.2), 265 (59.8), 280 (25.2)
As x-rays 1 (0.9), 11 (47.5), 12 (7.3)
Sr
50.53m
Se
S
74
Ge
S
Kr
10.72y
75
88
EC
Ga x-rays 1 (0.67), 9 (38.7), 10 (5.46)
+
â
822 (0.012), 1899 (0.8794)
ã
1077 (0.032), 1883 (0.0014)
Zn x-rays 9 (0.049), 10 (0.00579
173 (0.437), 687 (99.563)
514 (0.434)
As
17.77d
85
68
-
â
ã
â
1353 (34.0)
ã
634 (15.4)
EC
+
â
1540 (66.0)
ã 596 (59.9), 608 (0.55), 1204 (0.287)
Ge x-rays 1 (0.26), 10 (15), 11 (2.22)
Y
S
Sr
28.9y
90
Y
64.00h
74
74
89
Sr
50.53m
As
17.77d
EC
Ga x-rays 1 (0.67), 9 (38.7), 10 (5.46)
+
â
822 (0.012), 1899 (0.8794)
ã
1077 (0.032), 1883 (0.0014)
Zn x-rays 9 (0.049), 10 (0.00579
Rb
Sr
17.772m S
Rb
15.15m
Ga
67.7m
68
Zn
S
68
Rb
S
88
-
68
Ge
270.9d
68
Ga
67.7m
89
-
173 (0.437), 687 (99.563)
514 (0.434)
-
2581 (13.3), 3479 (4.1), 5315 (78)
898 (14), 1836 (21.4), 2678 (1.96)
-
1275 (33), 2223 (34), 4503 (25)
1031 (58), 1248 (42), 2196 (13.3)
-
1491 (99.985)
av. 909 (0.02%)
-
546 (100)
-
519 (0.0115), 2284 (99.9885)
â
ã
â
ã
â
ã
â
ã
â
â
68
EC
Ga x-rays 1 (0.67), 9 (38.7), 10 (5.46)
+
â
822 (0.012), 1899 (0.8794)
ã
1077 (0.032), 1883 (0.0014)
Zn x-rays 9 (0.049), 10 (0.00579
74
â
1353 (34.0)
ã
634 (15.4)
EC
+
â
1540 (66.0)
ã 596 (59.9), 608 (0.55), 1204 (0.287)
Ge x-rays 1 (0.26), 10 (15), 11 (2.22)
75
EC
ã
136 (59.2), 265 (59.8), 280 (25.2)
As x-rays 1 (0.9), 11 (47.5), 12 (7.3)
Rb
S
88
-
85
88
89
Sr
50.53m
89
Y
S
89
90
Y
64.00h
90
Zr
S
90
-
-
173 (0.437), 687 (99.563)
514 (0.434)
-
2581 (13.3), 3479 (4.1), 5315 (78)
898 (14), 1836 (21.4), 2678 (1.96)
-
1275 (33), 2223 (34), 4503 (25)
1031 (58), 1248 (42), 2196 (13.3)
-
1491 (99.985)
av. 909 (0.02%)
-
546 (100)
-
519 (0.0115), 2284 (99.9885)
â
ã
â
ã
â
ã
â
ã
â
â
94
Nb
20.3E4y
95
Zr
63.98d
94
Mo
S
-
471 (100)
703 (100), 871 (100)
Nb
20.3E4y
-
366 (55.4), 399 (43.7), 887 (0.78)
724 (43.7), 757 (55.3)
Zr
63.98d
-
160 (99.97)
766 (100)
Nb
34.991d
â
ã
95
Nb
34.991d
95
Mo
S
99
decays 88.6% to Tc
& 11.4% to Tc
â
436 (17.3), 848 (1.36), 1214 (82.7)
ã
181 (6.2), 740 (12.8), 778 (4.5)
Tc x-rays 2 (0.2), 18 (2.63), 21 (0.52)
Tc99
ã
141 (89.07)
2.13E5y Tc x-rays 2 (0.48), 18 (6.1), 21 (1.2)
99
Ru
â
294 (99.998)
S
Nb
34.991d
Mo
66.0h
Tc99m
6.0058h
99
Tc
2.13E5y
106
Ru
371.8d
106
Rh
29.9s
95
â
ã
94
99m
106
Te
S
126
Xe
S
I
12.928d
126
126
94
95
Zr
63.98d
â
EC
ã
35 (6.49)
Te x-rays 4 (15), 27 (112.2), 31 (25.4)
-
â
1258 (47.3)
ã 389(32.1), 491(2.43), 666(29.1), 754 (3.7)
Xe x-rays 29 (0.115), 30 (0.213)
+
â
1132 (52.7)
Te x-rays 4 (4.8), 27 (36.4), 31 (8.2)
94
Nb
34.991d
99m
106
Ru
371.8d
106
Rh
29.9s
106
Rh
29.9s
106
Pd
S
125
Te
S
126
Xe
S
I
60.14d
I
12.928d
125
126
126
Te
S
Xe
S
Nb
34.991d
-
â
39 (100)
-
â 1979 (1.77), 2410 (10.6), 3541 (86.8)
ã
616 (0.75), 622 (9.93), 873 (0.439),
1050 (1.56), 1128 (0.404), 1562 (0.163)
EC
ã
35 (6.49)
Te x-rays 4 (15), 27 (112.2), 31 (25.4)
-
â
1258 (47.3)
ã 389(32.1), 491(2.43), 666(29.1), 754 (3.7)
Xe x-rays 29 (0.115), 30 (0.213)
+
â
1132 (52.7)
Te x-rays 4 (4.8), 27 (36.4), 31 (8.2)
126
126
160 (99.97)
766 (100)
99
-
160 (99.97)
766 (100)
95
â
Mo
S
EC
ã
35 (6.49)
Te x-rays 4 (15), 27 (112.2), 31 (25.4)
-
â
1258 (47.3)
ã 389(32.1), 491(2.43), 666(29.1), 754 (3.7)
Xe x-rays 29 (0.115), 30 (0.213)
+
â
1132 (52.7)
Te x-rays 4 (4.8), 27 (36.4), 31 (8.2)
-
471 (100)
703 (100), 871 (100)
-
366 (55.4), 399 (43.7), 887 (0.78)
724 (43.7), 757 (55.3)
-
160 (99.97)
766 (100)
â
ã
Nb
34.991d
â
ã
95
Mo
S
99
decays 88.6% to Tc
& 11.4% to Tc
â
436 (17.3), 848 (1.36), 1214 (82.7)
ã
181 (6.2), 740 (12.8), 778 (4.5)
Tc x-rays 2 (0.2), 18 (2.63), 21 (0.52)
99
Tc
ã
141 (89.07)
2.13E5y Tc x-rays 2 (0.48), 18 (6.1), 21 (1.2)
99
Ru
â
294 (99.998)
S
Mo
66.0h
99m
Tc
6.0058h
99
Tc
2.13E5y
106
Ru
371.8d
106
Rh
29.9s
106
Rh
29.9s
106
Pd
S
Te
S
126
Xe
S
I
12.928d
â
ã
99m
125
I
60.14d
95
39 (100)
-
94
95
-
99
â 1979 (1.77), 2410 (10.6), 3541 (86.8)
ã
616 (0.75), 622 (9.93), 873 (0.439),
1050 (1.56), 1128 (0.404), 1562 (0.163)
125
Te
S
-
99m
366 (55.4), 399 (43.7), 887 (0.78)
724 (43.7), 757 (55.3)
â
ã
106
126
I
12.928d
95
Rh
29.9s
106
Pd
S
Te
S
Zr
63.98d
â
ã
-
â
ã
99m
125
I
60.14d
366 (55.4), 399 (43.7), 887 (0.78)
724 (43.7), 757 (55.3)
decays 88.6% to Tc
& 11.4% to Tc
â
436 (17.3), 848 (1.36), 1214 (82.7)
ã
181 (6.2), 740 (12.8), 778 (4.5)
Tc x-rays 2 (0.2), 18 (2.63), 21 (0.52)
99
Tc
ã
141 (89.07)
2.13E5y Tc x-rays 2 (0.48), 18 (6.1), 21 (1.2)
99
Ru
â
294 (99.998)
S
Tc
6.0058h
99
Tc
2.13E5y
Ru
371.8d
106
Rh
29.9s
-
99
Mo
66.0h
95
Tc99m
6.0058h
99
Tc
2.13E5y
94
Mo
S
95
Nb
34.991d
decays 88.6% to Tc
& 11.4% to Tc
â
436 (17.3), 848 (1.36), 1214 (82.7)
ã
181 (6.2), 740 (12.8), 778 (4.5)
Tc x-rays 2 (0.2), 18 (2.63), 21 (0.52)
Tc99
ã
141 (89.07)
2.13E5y Tc x-rays 2 (0.48), 18 (6.1), 21 (1.2)
99
Ru
â
294 (99.998)
S
Nb
20.3E4y
95
Nb
34.991d
471 (100)
703 (100), 871 (100)
99
Mo
66.0h
471 (100)
703 (100), 871 (100)
â
ã
-
â
ã
Mo
S
-
â
ã
94
95
106
39 (100)
-
Mo
S
95
99
â 1979 (1.77), 2410 (10.6), 3541 (86.8)
ã
616 (0.75), 622 (9.93), 873 (0.439),
1050 (1.56), 1128 (0.404), 1562 (0.163)
125
Te
S
Nb
20.3E4y
-
Rh
29.9s
106
Pd
S
125
I
60.14d
â
ã
95
Mo
S
125
126
126
Te
S
â
-
99
39 (100)
-
â 1979 (1.77), 2410 (10.6), 3541 (86.8)
ã
616 (0.75), 622 (9.93), 873 (0.439),
1050 (1.56), 1128 (0.404), 1562 (0.163)
EC
ã
35 (6.49)
Te x-rays 4 (15), 27 (112.2), 31 (25.4)
-
â
1258 (47.3)
ã 389(32.1), 491(2.43), 666(29.1), 754 (3.7)
Xe x-rays 29 (0.115), 30 (0.213)
+
â
1132 (52.7)
Te x-rays 4 (4.8), 27 (36.4), 31 (8.2)
129
Xe
S
129
â
194 (100)
ã
40 (7.52)
Xe x-rays 4 (12), 29 (29.7), 30 (55), 34 (19.6)
131
Xe
S
131
364 (81.2), 503 (0.36), 637 (7.26)
643 (0.22), 723 (1.80)
ã
284 (6.05), 364 (81.2), 637 (7.26)
Xe x-rays 4 (0.6), 29 (1.3), 30 (2.5), 34 (0.9)
133
Xe
5.248d
I
1.57E7y
I
8.025d
I
20.8h
133
133
Cs
133
134
I
52.6m
-
I
8.025d
-
I
20.8h
-
Xe
5.248d
370 (1.24), 460 (3.75), 520 (3.13),
880 (4.16), 1020 (1.81), 1230 (83.5)
1530 (1.07)
ã
511 (1.81), 530 (86.3), 707 (1.49),
856 (1.23), 875 (4.47), 1236 (1.49), 1298 (2.33)
Xe x-rays 29 (0.151), 30 (0.281)
Cs
S
Ba
10.518y
I
1.57E7y
â
133
133
Xe
5.248d
-
Xe
S
â
â
267 (0.69), 346 (99.3)
ã
530 (86.3), 875 (4.47), 1298 (2.33)
Cs x-rays 29 (45.7), 33 (10.6), 233 (10.3)
S
EC
ã
134
-
53 (2.14), 80 (35.55), 276 (6.9),
303 (17.8), 356 (60), 384 (8.7)
Cs x-rays 4 (17), 31 (97.6), 35 (22.8)
â 1280 (32.5), 1560 (16.3), 1800 (11.2),
2420 (11.5)
ã
847 (95.41), 884 (65.3),1073 (15.3)
Xe x-rays 4 (0.17), 29 (0.43), 30 (0.8), 34 (0.3)
129
Xe
S
129
â
194 (100)
ã
40 (7.52)
Xe x-rays 4 (12), 29 (29.7), 30 (55), 34 (19.6)
131
Xe
S
131
364 (81.2), 503 (0.36), 637 (7.26)
643 (0.22), 723 (1.80)
ã
284 (6.05), 364 (81.2), 637 (7.26)
Xe x-rays 4 (0.6), 29 (1.3), 30 (2.5), 34 (0.9)
133
Xe
5.248d
133
133
Cs
133
134
-
370 (1.24), 460 (3.75), 520 (3.13),
880 (4.16), 1020 (1.81), 1230 (83.5)
1530 (1.07)
ã
511 (1.81), 530 (86.3), 707 (1.49),
856 (1.23), 875 (4.47), 1236 (1.49), 1298 (2.33)
Xe x-rays 29 (0.151), 30 (0.281)
Cs
S
I
52.6m
-
â
133
133
Ba
10.518y
-
Xe
S
â
-
â
267 (0.69), 346 (99.3)
ã
530 (86.3), 875 (4.47), 1298 (2.33)
Cs x-rays 29 (45.7), 33 (10.6), 233 (10.3)
S
EC
ã
134
-
53 (2.14), 80 (35.55), 276 (6.9),
303 (17.8), 356 (60), 384 (8.7)
Cs x-rays 4 (17), 31 (97.6), 35 (22.8)
â 1280 (32.5), 1560 (16.3), 1800 (11.2),
2420 (11.5)
ã
847 (95.41), 884 (65.3),1073 (15.3)
Xe x-rays 4 (0.17), 29 (0.43), 30 (0.8), 34 (0.3)
54
129
Xe
S
129
â
194 (100)
ã
40 (7.52)
Xe x-rays 4 (12), 29 (29.7), 30 (55), 34 (19.6)
131
Xe
S
131
364 (81.2), 503 (0.36), 637 (7.26)
643 (0.22), 723 (1.80)
ã
284 (6.05), 364 (81.2), 637 (7.26)
Xe x-rays 4 (0.6), 29 (1.3), 30 (2.5), 34 (0.9)
133
Xe
5.248d
I
1.57E7y
I
8.025d
I
20.8h
133
Cs
S
133
133
Cs
133
Ba
10.518y
134
I
52.6m
Xe
S
129
Xe
S
129
â
194 (100)
ã
40 (7.52)
Xe x-rays 4 (12), 29 (29.7), 30 (55), 34 (19.6)
131
Xe
S
131
364 (81.2), 503 (0.36), 637 (7.26)
643 (0.22), 723 (1.80)
ã
284 (6.05), 364 (81.2), 637 (7.26)
Xe x-rays 4 (0.6), 29 (1.3), 30 (2.5), 34 (0.9)
133
Xe
5.248d
-
I
1.57E7y
-
I
8.025d
-
I
20.8h
-
Xe
5.248d
â
370 (1.24), 460 (3.75), 520 (3.13),
880 (4.16), 1020 (1.81), 1230 (83.5)
1530 (1.07)
ã
511 (1.81), 530 (86.3), 707 (1.49),
856 (1.23), 875 (4.47), 1236 (1.49), 1298 (2.33)
Xe x-rays 29 (0.151), 30 (0.281)
133
Xe
5.248d
54
â
â
267 (0.69), 346 (99.3)
ã
530 (86.3), 875 (4.47), 1298 (2.33)
Cs x-rays 29 (45.7), 33 (10.6), 233 (10.3)
S
EC
ã
134
-
53 (2.14), 80 (35.55), 276 (6.9),
303 (17.8), 356 (60), 384 (8.7)
Cs x-rays 4 (17), 31 (97.6), 35 (22.8)
â 1280 (32.5), 1560 (16.3), 1800 (11.2),
2420 (11.5)
ã
847 (95.41), 884 (65.3),1073 (15.3)
Xe x-rays 4 (0.17), 29 (0.43), 30 (0.8), 34 (0.3)
54
133
Cs
S
133
133
Cs
133
134
I
52.6m
-
â
-
370 (1.24), 460 (3.75), 520 (3.13),
880 (4.16), 1020 (1.81), 1230 (83.5)
1530 (1.07)
ã
511 (1.81), 530 (86.3), 707 (1.49),
856 (1.23), 875 (4.47), 1236 (1.49), 1298 (2.33)
Xe x-rays 29 (0.151), 30 (0.281)
133
Ba
10.518y
-
Xe
S
â
-
â
267 (0.69), 346 (99.3)
ã
530 (86.3), 875 (4.47), 1298 (2.33)
Cs x-rays 29 (45.7), 33 (10.6), 233 (10.3)
S
EC
ã
134
-
53 (2.14), 80 (35.55), 276 (6.9),
303 (17.8), 356 (60), 384 (8.7)
Cs x-rays 4 (17), 31 (97.6), 35 (22.8)
â 1280 (32.5), 1560 (16.3), 1800 (11.2),
2420 (11.5)
ã
847 (95.41), 884 (65.3),1073 (15.3)
Xe x-rays 4 (0.17), 29 (0.43), 30 (0.8), 34 (0.3)
54
135
I
6.583h
135
Xe
9.139h
135
Cs
2.31E6y
135
Ba
S
137
Ba
2.552m
137
Ba
S
Xe
9.139h
Cs
2.31E6y
Cs
30.187y
137m
Ba
2.552m
140
Ba
12.75d
140
La
1.68d
148
Gd
74.52y
135
135
137m
140
La
1.68d
-
â
300 (1.08), 340 (0.91), 350 (1.39),
460 (4.73), 480 (7.33), 620 (1.57),
670 (1.10), 740 (7.9), 920 (8.7),
1030 (21.8), 1150 (7.9), 1250 (7.4),
1450 (23.6), 1580 (1.2), 2180 (1.9)
ã 1132 (22.5), 1260 (28.6), 1678 (9.5)
Xe x-rays 30 (0.127)
â
551 (3.13), 751 (0.59), 909 (96.1)
ã
158 (0.29), 249 (89.9), 358 (0.22),
408 (0.36), 608 (2.89)
Cs x-rays 4 (0.66), 31 (4.13), 35 (0.96)
â
269 (100)
ã
268 (16.0)
Ba x-rays 4 (8.6), 32 (43.6), 36 (10.3)
-
â
512 (94.6), 1173 (5.4)
IT
ã
662 (89.98)
Ba x-rays 4 (1), 32 (5.89), 36 (1.39)
-
â
454 (26), 991 (37.4), 1005 (22)
ã
30 (14), 163 (6.7), 537 (25)
La x-rays 5 (15), 33 (1.51), 38 (0.36)
140
Ce
â
1239 (11.11), 1348 (44.5),
S
1677 (20.7)
ã
329 (20.5), 487 (45.5), 816 (23.5)
Ce x-rays 5 (0.25), 34 (0.47), 35 (0.9), 39 (0.9)
144
Sm
á
6.98E15y
3180 (100)
135
I
6.583h
135
Xe
9.139h
135
Cs
2.31E6y
135
Ba
S
137
Ba
2.552m
137
Ba
S
Xe
9.139h
Cs
2.31E6y
Cs
30.187y
137m
Ba
2.552m
140
Ba
12.75d
140
La
1.68d
148
Gd
74.52y
135
135
137m
140
La
1.68d
-
â
300 (1.08), 340 (0.91), 350 (1.39),
460 (4.73), 480 (7.33), 620 (1.57),
670 (1.10), 740 (7.9), 920 (8.7),
1030 (21.8), 1150 (7.9), 1250 (7.4),
1450 (23.6), 1580 (1.2), 2180 (1.9)
ã 1132 (22.5), 1260 (28.6), 1678 (9.5)
Xe x-rays 30 (0.127)
â
551 (3.13), 751 (0.59), 909 (96.1)
ã
158 (0.29), 249 (89.9), 358 (0.22),
408 (0.36), 608 (2.89)
Cs x-rays 4 (0.66), 31 (4.13), 35 (0.96)
â
269 (100)
ã
268 (16.0)
Ba x-rays 4 (8.6), 32 (43.6), 36 (10.3)
-
â
IT
ã
662 (89.98)
Ba x-rays 4 (1), 32 (5.89), 36 (1.39)
-
â
454 (26), 991 (37.4), 1005 (22)
ã
30 (14), 163 (6.7), 537 (25)
La x-rays 5 (15), 33 (1.51), 38 (0.36)
140
Ce
â
1239 (11.11), 1348 (44.5),
S
1677 (20.7)
ã
329 (20.5), 487 (45.5), 816 (23.5)
Ce x-rays 5 (0.25), 34 (0.47), 35 (0.9), 39 (0.9)
144
Sm
á
6.98E15y
55
135
I
6.583h
135
Xe
9.139h
135
Cs
2.31E6y
135
Ba
S
137
Ba
2.552m
137
Ba
S
Xe
9.139h
Cs
2.31E6y
Cs
30.187y
137m
Ba
2.552m
140
Ba
12.75d
140
La
1.68d
148
Gd
74.52y
135
135
137m
140
La
1.68d
-
â
300 (1.08), 340 (0.91), 350 (1.39),
460 (4.73), 480 (7.33), 620 (1.57),
670 (1.10), 740 (7.9), 920 (8.7),
1030 (21.8), 1150 (7.9), 1250 (7.4),
1450 (23.6), 1580 (1.2), 2180 (1.9)
ã 1132 (22.5), 1260 (28.6), 1678 (9.5)
Xe x-rays 30 (0.127)
â
551 (3.13), 751 (0.59), 909 (96.1)
ã
158 (0.29), 249 (89.9), 358 (0.22),
408 (0.36), 608 (2.89)
Cs x-rays 4 (0.66), 31 (4.13), 35 (0.96)
â
269 (100)
ã
268 (16.0)
Ba x-rays 4 (8.6), 32 (43.6), 36 (10.3)
-
â
512 (94.6), 1173 (5.4)
IT
ã
662 (89.98)
Ba x-rays 4 (1), 32 (5.89), 36 (1.39)
-
â
454 (26), 991 (37.4), 1005 (22)
ã
30 (14), 163 (6.7), 537 (25)
La x-rays 5 (15), 33 (1.51), 38 (0.36)
140
Ce
â
1239 (11.11), 1348 (44.5),
S
1677 (20.7)
ã
329 (20.5), 487 (45.5), 816 (23.5)
Ce x-rays 5 (0.25), 34 (0.47), 35 (0.9), 39 (0.9)
144
Sm
á
6.98E15y
3180 (100)
55
512 (94.6), 1173 (5.4)
3180 (100)
55
135
I
6.583h
135
Xe
9.139h
135
Cs
2.31E6y
135
Ba
S
137
Ba
2.552m
137
Ba
S
Xe
9.139h
Cs
2.31E6y
Cs
30.187y
137m
Ba
2.552m
140
Ba
12.75d
140
La
1.68d
148
Gd
74.52y
135
135
137m
140
La
1.68d
-
â
300 (1.08), 340 (0.91), 350 (1.39),
460 (4.73), 480 (7.33), 620 (1.57),
670 (1.10), 740 (7.9), 920 (8.7),
1030 (21.8), 1150 (7.9), 1250 (7.4),
1450 (23.6), 1580 (1.2), 2180 (1.9)
ã 1132 (22.5), 1260 (28.6), 1678 (9.5)
Xe x-rays 30 (0.127)
â
551 (3.13), 751 (0.59), 909 (96.1)
ã
158 (0.29), 249 (89.9), 358 (0.22),
408 (0.36), 608 (2.89)
Cs x-rays 4 (0.66), 31 (4.13), 35 (0.96)
â
269 (100)
ã
268 (16.0)
Ba x-rays 4 (8.6), 32 (43.6), 36 (10.3)
-
â
512 (94.6), 1173 (5.4)
IT
ã
662 (89.98)
Ba x-rays 4 (1), 32 (5.89), 36 (1.39)
-
â
454 (26), 991 (37.4), 1005 (22)
ã
30 (14), 163 (6.7), 537 (25)
La x-rays 5 (15), 33 (1.51), 38 (0.36)
140
Ce
â
1239 (11.11), 1348 (44.5),
S
1677 (20.7)
ã
329 (20.5), 487 (45.5), 816 (23.5)
Ce x-rays 5 (0.25), 34 (0.47), 35 (0.9), 39 (0.9)
144
Sm
á
6.98E15y
3180 (100)
55
192
Ir
73.83d
204
Tl
3.779y
204m
Pb
66.9m
192
Pt
S
-
Ir
73.83d
â 256 (5.65), 536 (41.4), 672 (48.3)
ã 296 (29.02), 308 (29.68), 317 (82.85),
468 (48.1), 589 (4.57), 604 (8.20), 612 (5.34)
Pt x-rays 9 (4.1), 65 (2.6), 67 (4.5), 76 (1.97)
Os192
EC (4.69%)
S Os x-rays 9 (1.46), 61 (1.1), 63 (1.96), 71 (0.8)
-
Tl
3.779y
204
Pb
â
763 (97.42)
66.9m
204
Hg
EC (2.58)
S
Hg x-rays 10 (0.8), 69 (0.4), 71 (0.7), 80 (0.3)
204
Pb
IT
S
ã
375 (94.11), 899 (99.2), 912 (91.1)
Pb x-rays 11 (4.9), 73 (2.8), 75 (4.36), 85 (1.94)
â 256 (5.65), 536 (41.4), 672 (48.3)
ã 296 (29.02), 308 (29.68), 317 (82.85),
468 (48.1), 589 (4.57), 604 (8.20), 612 (5.34)
Pt x-rays 9 (4.1), 65 (2.6), 67 (4.5), 76 (1.97)
Os192
EC (4.69%)
S Os x-rays 9 (1.46), 61 (1.1), 63 (1.96), 71 (0.8)
204m
Pb
â
763 (97.42)
66.9m
204
Hg
EC (2.58)
S
Hg x-rays 10 (0.8), 69 (0.4), 71 (0.7), 80 (0.3)
204
Pb
IT
S
ã
375 (94.11), 899 (99.2), 912 (91.1)
Pb x-rays 11 (4.9), 73 (2.8), 75 (4.36), 85 (1.94)
208
208
212
212
212
206
206
210
210
210
216
220
224
Pb (S), Tl , Po , Bi , Pb , Po , Rn , Ra , Th
228
228
232
Ac , Ra , Th are in the Thorium-232 decay chain.
210
214
214
228
,
209
209
213
213
217
221
225
207
211
211
211
215
215
192
-
204m
-
208
208
212
212
212
206
206
210
210
210
216
220
224
Pb (S), Tl , Po , Bi , Pb , Po , Rn , Ra , Th
228
228
232
Ac , Ra , Th are in the Thorium-232 decay chain.
225
Bi (S), Tl , Pb , Po , Bi , At , Fr , Ac , Ra
229
233
233
237
237
241
241
Th , U , Pa , U , Np , Am , Pu are in the
Neptunium (4n+1) decay chain.
209
,
219
209
207
207
209
213
211
211
213
211
210
217
215
214
221
215
214
225
Pb
(S), Tl , Po , Bi , Pb , At , Po , Rn ,
223
223
227
227
231
231
235
Ra , Fr , Th , Ac , Pa , Th , U are in the
Actinium (4n+3) decay chain.
Refer to those decay chains for information on these
isotopes.
Refer to those decay chains for information on these
isotopes.
192
204
Tl
3.779y
204m
Pb
66.9m
192
Pt
S
204m
Ir
73.83d
-
Tl
3.779y
Pb
â
763 (97.42)
66.9m
204
Hg
EC (2.58)
S
Hg x-rays 10 (0.8), 69 (0.4), 71 (0.7), 80 (0.3)
204
Pb
IT
S
ã
375 (94.11), 899 (99.2), 912 (91.1)
Pb x-rays 11 (4.9), 73 (2.8), 75 (4.36), 85 (1.94)
208
208
212
212
212
206
206
210
210
210
216
220
224
Pb (S), Tl , Po , Bi , Pb , Po , Rn , Ra , Th
228
228
232
Ac , Ra , Th are in the Thorium-232 decay chain.
210
214
214
228
209
209
213
213
217
221
225
207
211
211
211
215
215
219
204m
Pb
66.9m
192
225
,
-
â 256 (5.65), 536 (41.4), 672 (48.3)
ã 296 (29.02), 308 (29.68), 317 (82.85),
468 (48.1), 589 (4.57), 604 (8.20), 612 (5.34)
Pt x-rays 9 (4.1), 65 (2.6), 67 (4.5), 76 (1.97)
Os192
EC (4.69%)
S Os x-rays 9 (1.46), 61 (1.1), 63 (1.96), 71 (0.8)
204m
-
Pb
â
763 (97.42)
66.9m
204
Hg
EC (2.58)
S
Hg x-rays 10 (0.8), 69 (0.4), 71 (0.7), 80 (0.3)
204
Pb
IT
S
ã
375 (94.11), 899 (99.2), 912 (91.1)
Pb x-rays 11 (4.9), 73 (2.8), 75 (4.36), 85 (1.94)
208
208
212
212
212
206
206
210
210
210
216
220
224
Pb (S), Tl , Po , Bi , Pb , Po , Rn , Ra , Th
228
228
232
Ac , Ra , Th are in the Thorium-232 decay chain.
210
214
214
228
214
Pb (S), Tl , Po , Bi , Pb , Tl , Po , Bi , Pb ,
218
218
222
226
230
234
234
234m
234
At , Po , Rn , Ra , Th , U , Pa , Pa
, Th ,
238
U
are in the Uranium-238 decay chain.
225
Bi (S), Tl , Pb , Po , Bi , At , Fr , Ac , Ra
229
233
233
237
237
241
241
Th , U , Pa , U , Np , Am , Pu are in the
Neptunium (4n+1) decay chain.
Bi (S), Tl , Pb , Po , Bi , At , Fr , Ac , Ra
229
233
233
237
237
241
241
Th , U , Pa , U , Np , Am , Pu are in the
Neptunium (4n+1) decay chain.
207
,
204
Pt
S
214
214
Pb (S), Tl , Po , Bi , Pb , Tl , Po , Bi , Pb ,
218
218
222
226
230
234
234
234m
234
At , Po , Rn , Ra , Th , U , Pa , Pa
, Th ,
238
U
are in the Uranium-238 decay chain.
209
192
-
â 256 (5.65), 536 (41.4), 672 (48.3)
ã 296 (29.02), 308 (29.68), 317 (82.85),
468 (48.1), 589 (4.57), 604 (8.20), 612 (5.34)
Pt x-rays 9 (4.1), 65 (2.6), 67 (4.5), 76 (1.97)
Os192
EC (4.69%)
S Os x-rays 9 (1.46), 61 (1.1), 63 (1.96), 71 (0.8)
,
209
207
,
219
Pb
(S), Tl , Po , Bi , Pb , At , Po , Rn ,
223
223
227
227
231
231
235
Ra , Fr , Th , Ac , Pa , Th , U are in the
Actinium (4n+3) decay chain.
Ir
73.83d
228
Pb (S), Tl , Po , Bi , Pb , Tl , Po , Bi , Pb ,
218
218
222
226
230
234
234
234m
234
At , Po , Rn , Ra , Th , U , Pa , Pa
, Th ,
238
U
are in the Uranium-238 decay chain.
Bi (S), Tl , Pb , Po , Bi , At , Fr , Ac , Ra
229
233
233
237
237
241
241
Th , U , Pa , U , Np , Am , Pu are in the
Neptunium (4n+1) decay chain.
207
204m
Pb
66.9m
Pt
S
214
Pb (S), Tl , Po , Bi , Pb , Tl , Po , Bi , Pb ,
218
218
222
226
230
234
234
234m
234
At , Po , Rn , Ra , Th , U , Pa , Pa
, Th ,
238
U
are in the Uranium-238 decay chain.
209
192
209
207
209
211
213
211
213
211
217
215
221
215
225
219
Pb
(S), Tl , Po , Bi , Pb , At , Po , Rn ,
223
223
227
227
231
231
235
Ra , Fr , Th , Ac , Pa , Th , U are in the
Actinium (4n+3) decay chain.
Pb
(S), Tl , Po , Bi , Pb , At , Po , Rn ,
223
223
227
227
231
231
235
Ra , Fr , Th , Ac , Pa , Th , U are in the
Actinium (4n+3) decay chain.
Refer to those decay chains for information on these
isotopes.
Refer to those decay chains for information on these
isotopes.
225
,
,
236
Pu
2.851y
232
U
68.9y
242
232
U
4.47E9y
á 5614 (0.2), 5722 (31.8), 5770 (68.1)
ã
av. 61 (0.08)
U x-rays 14 (13)
228
Th
á
5270 (32), 5320 (68)
1.41E10y ã 58 (0.21), 129 (0.082), 270 (0.0038),
328 (0.0034)
Th x-rays 13 (39), 90 (0.21), 93 (3.5),105 (1.6)
238
Pu
U
3.742E5y 4.47E9y
242
Cm
162.85d
238
Pu
87.84y
238
Pu
87.84y
234
U
4.47E9y
243
239
244
Pu
6567.1y
Cm
162.85d
U
4.47E9y
242
236
232
238
Pu
U
3.742E5y 4.47E9y
242
Cm
162.85d
238
Pu
87.84y
238
Pu
87.84y
234
U
4.47E9y
243
239
244
Pu
6567.1y
240
Pu
6567.1y
243
239
244
Pu
6567.1y
236
U
2.34E7y
240
Pu
6567.1y
240
U
2.34E7y
236
U
4.47E9y
232
U
68.9y
242
236
á 5614 (0.2), 5722 (31.8), 5770 (68.1)
ã
av. 61 (0.08)
U x-rays 14 (13)
228
Th
á
5270 (32), 5320 (68)
1.41E10y ã 58 (0.21), 129 (0.082), 270 (0.0038),
328 (0.0034)
Th x-rays 13 (39), 90 (0.21), 93 (3.5),105 (1.6)
238
Cm
162.85d
242
238
Pu
87.84y
á
5763 (23.6), 5805 (76.4)
ã
av. 57 (0.03)
Pu x-rays 14 (10.3)
á
5763 (23.6), 5805 (76.4)
ã
av. 57 (0.03)
232
á
6070 (25.9), 6113 (74.1)
ã
av. 59 (0.04)
Pu x-rays 14 (11.5)
á
5593 (100)
U x-rays 14 (9.1)
á
5763 (23.6), 5805 (76.4)
ã
av. 57 (0.03)
Pu x-rays 14 (10.3)
á
5763 (23.6), 5805 (76.4)
ã
av. 57 (0.03)
á
6070 (25.9), 6113 (74.1)
ã
av. 59 (0.04)
Pu x-rays 14 (11.5)
á
5593 (100)
U x-rays 14 (9.1)
á
5181 (1), 5234 (10.6), 5275 (87.9)
ã
43 (5.5), 75 (66), 118 (0.55)
Np x-rays 14 (39)
239
239
Np
Pu
â
330 (35.7), 391 (7.1), 436 (52)
2.3565d 24,125y ã
106 (22.7), 228 (10.7), 278 (14.1)
Pu x-rays 14 (62), 100 (14.7), 104 (23.7),117 (11.1)
239
235
Pu
U
á 5358 (0.1), 5456 (28.3), 5499 (71.6)
24,125y 7.08E8y ã 44 (0.039), 100 (0.008), 153 (0.001)
U x-rays 14 (11.6)
Pu
U
3.742E5y 4.47E9y
á
5181 (1), 5234 (10.6), 5275 (87.9)
ã
43 (5.5), 75 (66), 118 (0.55)
Np x-rays 14 (39)
239
239
Np
Pu
â
330 (35.7), 391 (7.1), 436 (52)
2.3565d 24,125y ã
106 (22.7), 228 (10.7), 278 (14.1)
Pu x-rays 14 (62), 100 (14.7), 104 (23.7),117 (11.1)
239
235
Pu
U
á 5358 (0.1), 5456 (28.3), 5499 (71.6)
24,125y 7.08E8y ã 44 (0.039), 100 (0.008), 153 (0.001)
U x-rays 14 (11.6)
240
234
U
4.47E9y
á
4856 (22.4), 4901 (78)
ã
av. 4753 (0.1)
U x-rays 14 (9.1)
Am
Np
7.388E3y 2.3565d
Cm
18.11y
238
Pu
87.84y
á
4856 (22.4), 4901 (78)
ã
av. 4753 (0.1)
U x-rays 14 (9.1)
Am
Np
7.388E3y 2.3565d
Pu
2.851y
236
232
238
Pu
87.84y
á 5614 (0.2), 5722 (31.8), 5770 (68.1)
ã
av. 61 (0.08)
U x-rays 14 (13)
228
Th
á
5270 (32), 5320 (68)
1.41E10y ã 58 (0.21), 129 (0.082), 270 (0.0038),
328 (0.0034)
Th x-rays 13 (39), 90 (0.21), 93 (3.5),105 (1.6)
U
2.34E7y
U
68.9y
242
Cm
18.11y
240
238
á
6070 (25.9), 6113 (74.1)
ã
av. 59 (0.04)
Pu x-rays 14 (11.5)
á
5593 (100)
U x-rays 14 (9.1)
á
5763 (23.6), 5805 (76.4)
ã
av. 57 (0.03)
Pu x-rays 14 (10.3)
á
5763 (23.6), 5805 (76.4)
ã
av. 57 (0.03)
Pu
6567.1y
Pu
2.851y
242
á 5614 (0.2), 5722 (31.8), 5770 (68.1)
ã
av. 61 (0.08)
U x-rays 14 (13)
228
Th
á
5270 (32), 5320 (68)
1.41E10y ã 58 (0.21), 129 (0.082), 270 (0.0038),
328 (0.0034)
Th x-rays 13 (39), 90 (0.21), 93 (3.5),105 (1.6)
Pu
U
3.742E5y 4.47E9y
á
5181 (1), 5234 (10.6), 5275 (87.9)
ã
43 (5.5), 75 (66), 118 (0.55)
Np x-rays 14 (39)
239
239
Np
Pu
â
330 (35.7), 391 (7.1), 436 (52)
2.3565d 24,125y ã
106 (22.7), 228 (10.7), 278 (14.1)
Pu x-rays 14 (62), 100 (14.7), 104 (23.7),117 (11.1)
239
235
Pu
U
á 5358 (0.1), 5456 (28.3), 5499 (71.6)
24,125y 7.08E8y ã 44 (0.039), 100 (0.008), 153 (0.001)
U x-rays 14 (11.6)
240
232
U
68.9y
232
U
4.47E9y
á
4856 (22.4), 4901 (78)
ã
av. 4753 (0.1)
U x-rays 14 (9.1)
Am
Np
7.388E3y 2.3565d
Cm
18.11y
236
Pu
2.851y
238
Pu
87.84y
234
U
4.47E9y
243
239
244
Pu
6567.1y
á
4856 (22.4), 4901 (78)
ã
av. 4753 (0.1)
U x-rays 14 (9.1)
á
6070 (25.9), 6113 (74.1)
ã
av. 59 (0.04)
Pu x-rays 14 (11.5)
á
5593 (100)
U x-rays 14 (9.1)
Am
Np
7.388E3y 2.3565d
á
5181 (1), 5234 (10.6), 5275 (87.9)
ã
43 (5.5), 75 (66), 118 (0.55)
Np x-rays 14 (39)
239
239
Np
Pu
â
330 (35.7), 391 (7.1), 436 (52)
2.3565d 24,125y ã
106 (22.7), 228 (10.7), 278 (14.1)
Pu x-rays 14 (62), 100 (14.7), 104 (23.7),117 (11.1)
239
235
Pu
U
á 5358 (0.1), 5456 (28.3), 5499 (71.6)
24,125y 7.08E8y ã 44 (0.039), 100 (0.008), 153 (0.001)
U x-rays 14 (11.6)
Cm
18.11y
240
Pu
6567.1y
240
236
U
2.34E7y
á
5763 (23.6), 5805 (76.4)
ã
av. 57 (0.03)
Pu x-rays 14 (10.3)
á
5763 (23.6), 5805 (76.4)
ã
av. 57 (0.03)
249
Bk
320d
249
Cf
350.6y
245
Cm
350.6y
252
Cf
2.639y
248
Cm
333.5d
244
Pu
8.26E7y
240
U
14.1h
240
Np
7.4m
249
Cf
â126 (100)
350.6d
245
Cm
á
5760 (3.66), 5814 (84.4), 5946 (4)
8.5E3y
ã
253 (2.7), 333 (15.5), 388 (66)
Cm x-rays 15(30), 105 (2.19), 109 (3.5), 123 (1.66)
241
Pu
á
5304 (5), 5362 (93.18), 5488 (0.83)
24,125y ã
133 (6.3), 174 (6.4)
Pu x-rays 14 (64), 100 (14), 104 (22),
117 (10), 133 (6.3), 174 (6.4)
248
Cm
333.5d
á 5977 (0.2), 6076 (15.2), 6118 (81.6)
ã
av. 68 (0.03)
Cm x-rays 15 (7.3)
spontaneous fission (3)
244
Pu
á 5035 (16.54), 5077 (75.1)
8.26E7y ã
av. 68 (0.03)
Pu x-rays 14 (7.3)
spontaneous fission (8.26)
240
U
á 5035 (16.54), 5077 (75.1)
14.1h
ã
av. 68 (0.03)
Pu x-rays 14 (7.3)
spontaneous fission (8.26)
240
Np
â
440 (100)
7.4m
ã
44 (1.65)
Np x-rays 14 (4.4)
240
Pu
â 570 (2.22), 1150 (1.18), 1170 (1.45),
6567.1
y 1210 (3.5), 1250 (2.65), 1510 (31.9),
2070 (52)
ã av. 68 (0.03)
Pu x-rays 14 (34), 100 (0.129), 104 (0.208)
249
Bk
320d
249
Cf
350.6y
245
Cm
350.6y
252
Cf
2.639y
248
Cm
333.5d
244
Pu
8.26E7y
240
U
14.1h
240
Np
7.4m
249
Cf
â126 (100)
350.6d
245
Cm
á
5760 (3.66), 5814 (84.4), 5946 (4)
8.5E3y
ã
253 (2.7), 333 (15.5), 388 (66)
Cm x-rays 15(30), 105 (2.19), 109 (3.5), 123 (1.66)
241
Pu
á
5304 (5), 5362 (93.18), 5488 (0.83)
24,125y ã
133 (6.3), 174 (6.4)
Pu x-rays 14 (64), 100 (14), 104 (22),
117 (10), 133 (6.3), 174 (6.4)
248
Cm
333.5d
á 5977 (0.2), 6076 (15.2), 6118 (81.6)
ã
av. 68 (0.03)
Cm x-rays 15 (7.3)
spontaneous fission (3)
244
Pu
á 5035 (16.54), 5077 (75.1)
8.26E7y ã
av. 68 (0.03)
Pu x-rays 14 (7.3)
spontaneous fission (8.26)
240
U
á 5035 (16.54), 5077 (75.1)
14.1h
ã
av. 68 (0.03)
Pu x-rays 14 (7.3)
spontaneous fission (8.26)
240
Np
â
440 (100)
7.4m
ã
44 (1.65)
Np x-rays 14 (4.4)
240
Pu
â 570 (2.22), 1150 (1.18), 1170 (1.45),
6567.1
y 1210 (3.5), 1250 (2.65), 1510 (31.9),
2070 (52)
ã av. 68 (0.03)
Pu x-rays 14 (34), 100 (0.129), 104 (0.208)
58
249
Bk
320d
249
Cf
350.6y
245
Cm
350.6y
252
Cf
2.639y
248
Cm
333.5d
244
Pu
8.26E7y
240
U
14.1h
240
Np
7.4m
249
Cf
â126 (100)
350.6d
245
Cm
á
5760 (3.66), 5814 (84.4), 5946 (4)
8.5E3y
ã
253 (2.7), 333 (15.5), 388 (66)
Cm x-rays 15(30), 105 (2.19), 109 (3.5), 123 (1.66)
241
Pu
á
5304 (5), 5362 (93.18), 5488 (0.83)
24,125y ã
133 (6.3), 174 (6.4)
Pu x-rays 14 (64), 100 (14), 104 (22),
117 (10), 133 (6.3), 174 (6.4)
248
Cm
333.5d
á 5977 (0.2), 6076 (15.2), 6118 (81.6)
ã
av. 68 (0.03)
Cm x-rays 15 (7.3)
spontaneous fission (3)
244
Pu
á 5035 (16.54), 5077 (75.1)
8.26E7y ã
av. 68 (0.03)
Pu x-rays 14 (7.3)
spontaneous fission (8.26)
240
U
á 5035 (16.54), 5077 (75.1)
14.1h
ã
av. 68 (0.03)
Pu x-rays 14 (7.3)
spontaneous fission (8.26)
240
Np
â
440 (100)
7.4m
ã
44 (1.65)
Np x-rays 14 (4.4)
240
Pu
â 570 (2.22), 1150 (1.18), 1170 (1.45),
6567.1
y 1210 (3.5), 1250 (2.65), 1510 (31.9),
2070 (52)
ã av. 68 (0.03)
Pu x-rays 14 (34), 100 (0.129), 104 (0.208)
58
58
249
Bk
320d
249
Cf
350.6y
245
Cm
350.6y
252
Cf
2.639y
248
Cm
333.5d
244
Pu
8.26E7y
240
U
14.1h
240
Np
7.4m
249
Cf
â126 (100)
350.6d
245
Cm
á
5760 (3.66), 5814 (84.4), 5946 (4)
8.5E3y
ã
253 (2.7), 333 (15.5), 388 (66)
Cm x-rays 15(30), 105 (2.19), 109 (3.5), 123 (1.66)
241
Pu
á
5304 (5), 5362 (93.18), 5488 (0.83)
24,125y ã
133 (6.3), 174 (6.4)
Pu x-rays 14 (64), 100 (14), 104 (22),
117 (10), 133 (6.3), 174 (6.4)
248
Cm
333.5d
á 5977 (0.2), 6076 (15.2), 6118 (81.6)
ã
av. 68 (0.03)
Cm x-rays 15 (7.3)
spontaneous fission (3)
244
Pu
á 5035 (16.54), 5077 (75.1)
8.26E7y ã
av. 68 (0.03)
Pu x-rays 14 (7.3)
spontaneous fission (8.26)
240
U
á 5035 (16.54), 5077 (75.1)
14.1h
ã
av. 68 (0.03)
Pu x-rays 14 (7.3)
spontaneous fission (8.26)
240
Np
â
440 (100)
7.4m
ã
44 (1.65)
Np x-rays 14 (4.4)
240
Pu
â 570 (2.22), 1150 (1.18), 1170 (1.45),
6567.1
y 1210 (3.5), 1250 (2.65), 1510 (31.9),
2070 (52)
ã av. 68 (0.03)
Pu x-rays 14 (34), 100 (0.129), 104 (0.208)
58
Thorium-232 Decay Chain including thoron
1st Progeny
kev and % abundance
Thorium-232 Decay Chain including thoron
1st Progeny
kev and % abundance
Th232
Ra228
1.41E10y
á
3830 (0.2), 3953 (23), 4010 (77)
ã
59 (0.19), 125 (0.04)
Ra x-rays 12 (8.4)
Th232
Ra228
1.41E10y
á
3830 (0.2), 3953 (23), 4010 (77)
ã
59 (0.19), 125 (0.04)
Ra x-rays 12 (8.4)
Ra228
5.75y
Ac228
â-
Ra228
5.75y
Ac228
â-
Ac228
6.13h
Th228
â606 (8), 1168 (32), 1741 (12)
ã 338 (11.4), 911 (27.7), 969 (16.6)
Th x-rays 13 (39), 90 (2.1), 93 (3.5), 105
Ac228
6.13h
Th228
â606 (8), 1168 (32), 1741 (12)
ã 338 (11.4), 911 (27.7), 969 (16.6)
Th x-rays 13 (39), 90 (2.1), 93 (3.5), 105
39 (100)
(1.6)
39 (100)
(1.6)
228
224
Th
1.91y
Ra
á
5212 (0.4), 5341 (26.7), 5423 (72.7)
ã
84 (1.2), 132 (0.12), 216 (0.24)
Ra x-rays 12 (9.6)
Th228
1.91y
Ra224
á
5212 (0.4), 5341 (26.7), 5423 (72.7)
ã
84 (1.2), 132 (0.12), 216 (0.24)
Ra x-rays 12 (9.6)
Ra224
3.62d
Rn220
á
5449 (4.9), 5686 (95.1)
ã
241 (3.95)
Rn x-rays 12 (0.4), 81 (0.126), 84 (0.209)
Ra224
3.62d
Rn220
á
5449 (4.9), 5686 (95.1)
ã
241 (3.95)
Rn x-rays 12 (0.4), 81 (0.126), 84 (0.209)
Rn220 is “thoron” gas, usually included with “radon” gas
Rn220 is “thoron” gas, usually included with “radon” gas
Rn220
56s
Rn220
56s
Po216
á
ã
6288 (99.9), 5747 (0.1)
av. 550 (0.1)
Po216
á
ã
59
6288 (99.9), 5747 (0.1)
av. 550 (0.1)
59
Thorium-232 Decay Chain including thoron
1st Progeny
kev and % abundance
Thorium-232 Decay Chain including thoron
1st Progeny
kev and % abundance
Th232
Ra228
1.41E10y
á
3830 (0.2), 3953 (23), 4010 (77)
ã
59 (0.19), 125 (0.04)
Ra x-rays 12 (8.4)
Th232
Ra228
1.41E10y
á
3830 (0.2), 3953 (23), 4010 (77)
ã
59 (0.19), 125 (0.04)
Ra x-rays 12 (8.4)
Ra228
5.75y
Ac228
â-
Ra228
5.75y
Ac228
â-
Ac228
6.13h
Th228
â606 (8), 1168 (32), 1741 (12)
ã 338 (11.4), 911 (27.7), 969 (16.6)
Th x-rays 13 (39), 90 (2.1), 93 (3.5), 105
Ac228
6.13h
Th228
â606 (8), 1168 (32), 1741 (12)
ã 338 (11.4), 911 (27.7), 969 (16.6)
Th x-rays 13 (39), 90 (2.1), 93 (3.5), 105
39 (100)
(1.6)
228
39 (100)
(1.6)
224
Th
1.91y
Ra
á
5212 (0.4), 5341 (26.7), 5423 (72.7)
ã
84 (1.2), 132 (0.12), 216 (0.24)
Ra x-rays 12 (9.6)
Th228
1.91y
Ra224
á
5212 (0.4), 5341 (26.7), 5423 (72.7)
ã
84 (1.2), 132 (0.12), 216 (0.24)
Ra x-rays 12 (9.6)
Ra224
3.62d
Rn220
á
5449 (4.9), 5686 (95.1)
ã
241 (3.95)
Rn x-rays 12 (0.4), 81 (0.126), 84 (0.209)
Ra224
3.62d
Rn220
á
5449 (4.9), 5686 (95.1)
ã
241 (3.95)
Rn x-rays 12 (0.4), 81 (0.126), 84 (0.209)
Rn220 is “thoron” gas, usually included with “radon” gas
Rn220 is “thoron” gas, usually included with “radon” gas
Rn220
56s
Rn220
56s
Po216
á
ã
6288 (99.9), 5747 (0.1)
av. 550 (0.1)
59
Po216
á
ã
6288 (99.9), 5747 (0.1)
av. 550 (0.1)
59
Progeny
216
Po
0.15s
212
Pb
Pb212
Bi212
10.64h
kev and % abundance
á
6779 (99.998)
â158 (5.22), 334 (85.1), 573 (9.9)
ã
115 (0.6), 239 (44.6), 300 (3.4)
Bi x-rays 11 (15.5), 75 (10.7), 77 (18), 87 (8)
Progeny
Po216
0.15s
Pb212
Pb212
Bi212
10.64h
kev and % abundance
á
6779 (99.998)
â158 (5.22), 334 (85.1), 573 (9.9)
ã
115 (0.6), 239 (44.6), 300 (3.4)
Bi x-rays 11 (15.5), 75 (10.7), 77 (18), 87 (8)
Bi212 decays 64.07 % of the time by â- to Po212 and 35.93 % of
the time by á to Tl208
Bi212 decays 64.07 % of the time by â- to Po212 and 35.93 % of
the time by á to Tl208
Bi212
60.6m
Tl208
Po212
á
5767 (0.6), 6050 (25.2), 6090 (9.6)
â625 (3.4), 1519 (8), 2246 (48.4)
ã
727 (11.8), 785 (1.97), 1621 (2.75)
Tl x-rays 10 (7.7)
Bi212
60.6m
Tl208
Po212
á
5767 (0.6), 6050 (25.2), 6090 (9.6)
â625 (3.4), 1519 (8), 2246 (48.4)
ã
727 (11.8), 785 (1.97), 1621 (2.75)
Tl x-rays 10 (7.7)
Po212
304ns
Pb208
á
Po212
304ns
Pb208
á
Tl208
3.05m
Pb208
âã
Tl208
3.05m
Pb208
âã
8785 (100)
1283 (23.2), 1517 (22.7), 1794 (49.3)
511 (21.6), 583 (84.2), 860 (12.46),
2614 (99.8)
Pb x-rays 11 (2.9), 73 (2.0), 75 (3.4), 85 (1.5)
Pb208 is stable
1283 (23.2), 1517 (22.7), 1794 (49.3)
511 (21.6), 583 (84.2), 860 (12.46),
2614 (99.8)
Pb x-rays 11 (2.9), 73 (2.0), 75 (3.4), 85 (1.5)
Pb208 is stable
60
Progeny
Po216
0.15s
Pb212
Pb212
Bi212
10.64h
8785 (100)
60
kev and % abundance
á
6779 (99.998)
â158 (5.22), 334 (85.1), 573 (9.9)
ã
115 (0.6), 239 (44.6), 300 (3.4)
Bi x-rays 11 (15.5), 75 (10.7), 77 (18), 87 (8)
Progeny
Po216
0.15s
Pb212
Pb212
Bi212
10.64h
kev and % abundance
á
6779 (99.998)
â158 (5.22), 334 (85.1), 573 (9.9)
ã
115 (0.6), 239 (44.6), 300 (3.4)
Bi x-rays 11 (15.5), 75 (10.7), 77 (18), 87 (8)
Bi212 decays 64.07 % of the time by â- to Po212 and 35.93 % of
the time by á to Tl208
Bi212 decays 64.07 % of the time by â- to Po212 and 35.93 % of
the time by á to Tl208
Bi212
60.6m
Tl208
Po212
á
5767 (0.6), 6050 (25.2), 6090 (9.6)
â625 (3.4), 1519 (8), 2246 (48.4)
ã
727 (11.8), 785 (1.97), 1621 (2.75)
Tl x-rays 10 (7.7)
Bi212
60.6m
Tl208
Po212
á
5767 (0.6), 6050 (25.2), 6090 (9.6)
â625 (3.4), 1519 (8), 2246 (48.4)
ã
727 (11.8), 785 (1.97), 1621 (2.75)
Tl x-rays 10 (7.7)
Po212
304ns
Pb208
á
Po212
304ns
Pb208
á
Tl208
3.05m
Pb208
âã
Tl208
3.05m
Pb208
âã
8785 (100)
1283 (23.2), 1517 (22.7), 1794 (49.3)
511 (21.6), 583 (84.2), 860 (12.46),
2614 (99.8)
Pb x-rays 11 (2.9), 73 (2.0), 75 (3.4), 85 (1.5)
Pb208 is stable
8785 (100)
1283 (23.2), 1517 (22.7), 1794 (49.3)
511 (21.6), 583 (84.2), 860 (12.46),
2614 (99.8)
Pb x-rays 11 (2.9), 73 (2.0), 75 (3.4), 85 (1.5)
Pb208 is stable
60
60
Uranium-238 Decay (including Radon progeny)
1st Progeny
kev and % abundance
U238
Th234
á
4039 (0.2), 4147 (23.4), 4196 (77.4)
4.47E9y
ã
av. 66 (0.1)
Th x-rays 13 (8.8)
Uranium-238 Decay (including Radon progeny)
1st Progeny
kev and % abundance
U238
Th234
á
4039 (0.2), 4147 (23.4), 4196 (77.4)
4.47E9y
ã
av. 66 (0.1)
Th x-rays 13 (8.8)
Th234
24.1d
Th234
24.1d
Pa234m
â76 (2), 96 (25.3), 189 (72.5)
ã
63 (3.8), 92 (2.7), 93 (2.7)
Pa x-rays 13 (9.6)
Pa234m
â76 (2), 96 (25.3), 189 (72.5)
ã
63 (3.8), 92 (2.7), 93 (2.7)
Pa x-rays 13 (9.6)
Pa234m decays 99.87 % of the time by â- to U234 & 0.13 % of the
time by IT to Pa234
Pa234m decays 99.87 % of the time by â- to U234 & 0.13 % of the
time by IT to Pa234
Pa234m U234
1.17m
â1236 (0.7), 1471 (0.6), 2281 (98.6)
ã
766 (0.2), 926 (0.4), 1001 (0.6)
U x-rays 14 (0.44), 95 (0.115), 98 (0.187)
Pa234
IT
Pa234m U234
1.17m
U234
Pa234
6.70h
Pa234
6.70h
â484 (35), 654 (16), 1183 (10)
ã
131 (20.4), 882 (24), 946 (12)
U x-rays 14 (114), 95 (15.7), 98 (25.4), 111(11.8)
â1236 (0.7), 1471 (0.6), 2281 (98.6)
ã
766 (0.2), 926 (0.4), 1001 (0.6)
U x-rays 14 (0.44), 95 (0.115), 98 (0.187)
IT
Pa234
U234
â484 (35), 654 (16), 1183 (10)
ã
131 (20.4), 882 (24), 946 (12)
U x-rays 14 (114), 95 (15.7), 98 (25.4), 111(11.8)
U234
Th230
2.45E5y
á
4605 (0.2), 4724 (27.4), 4776 (72.4)
ã
53 (0.118), 121 (0.04)
Th x-rays 13 (10.5)
U234
Th230
2.45E5y
á
4605 (0.2), 4724 (27.4), 4776 (72.4)
ã
53 (0.118), 121 (0.04)
Th x-rays 13 (10.5)
Th230
Ra226
7.7E4y
á
4476 (0.12), 4621 (23.4), 4688 (76.3)
ã
68 (0.4), 168 (0.07)
Ra x-rays 12 (8.4)
Th230
Ra226
7.7E4y
á
4476 (0.12), 4621 (23.4), 4688 (76.3)
ã
68 (0.4), 168 (0.07)
Ra x-rays 12 (8.4)
Ra226
1600y
Rn222
á
4602 (5.6), 4785 (94.4)
ã
186 (3.28)
Rn x-rays 12 (0.8), 81 (0.18), 84 (0.3), 95 (0.14)
61
Ra226
1600y
Rn222
á
4602 (5.6), 4785 (94.4)
ã
186 (3.28)
Rn x-rays 12 (0.8), 81 (0.18), 84 (0.3), 95 (0.14)
61
Uranium-238 Decay (including Radon progeny)
1st Progeny
kev and % abundance
U238
Th234
á
4039 (0.2), 4147 (23.4), 4196 (77.4)
4.47E9y
ã
av. 66 (0.1)
Th x-rays 13 (8.8)
Uranium-238 Decay (including Radon progeny)
1st Progeny
kev and % abundance
U238
Th234
á
4039 (0.2), 4147 (23.4), 4196 (77.4)
4.47E9y
ã
av. 66 (0.1)
Th x-rays 13 (8.8)
Th234
24.1d
Th234
24.1d
Pa234m
â76 (2), 96 (25.3), 189 (72.5)
ã
63 (3.8), 92 (2.7), 93 (2.7)
Pa x-rays 13 (9.6)
Pa234m
â76 (2), 96 (25.3), 189 (72.5)
ã
63 (3.8), 92 (2.7), 93 (2.7)
Pa x-rays 13 (9.6)
Pa234m decays 99.87 % of the time by â- to U234 & 0.13 % of the
time by IT to Pa234
Pa234m decays 99.87 % of the time by â- to U234 & 0.13 % of the
time by IT to Pa234
Pa234m U234
1.17m
Pa234m U234
1.17m
Pa234
Pa234
6.70h
U234
â1236 (0.7), 1471 (0.6), 2281 (98.6)
ã
766 (0.2), 926 (0.4), 1001 (0.6)
U x-rays 14 (0.44), 95 (0.115), 98 (0.187)
IT
â484 (35), 654 (16), 1183 (10)
ã
131 (20.4), 882 (24), 946 (12)
U x-rays 14 (114), 95 (15.7), 98 (25.4), 111(11.8)
Pa234
Pa234
6.70h
U234
â1236 (0.7), 1471 (0.6), 2281 (98.6)
ã
766 (0.2), 926 (0.4), 1001 (0.6)
U x-rays 14 (0.44), 95 (0.115), 98 (0.187)
IT
â484 (35), 654 (16), 1183 (10)
ã
131 (20.4), 882 (24), 946 (12)
U x-rays 14 (114), 95 (15.7), 98 (25.4), 111(11.8)
U234
Th230
2.45E5y
á
4605 (0.2), 4724 (27.4), 4776 (72.4)
ã
53 (0.118), 121 (0.04)
Th x-rays 13 (10.5)
U234
Th230
2.45E5y
á
4605 (0.2), 4724 (27.4), 4776 (72.4)
ã
53 (0.118), 121 (0.04)
Th x-rays 13 (10.5)
Th230
Ra226
7.7E4y
á
4476 (0.12), 4621 (23.4), 4688 (76.3)
ã
68 (0.4), 168 (0.07)
Ra x-rays 12 (8.4)
Th230
Ra226
7.7E4y
á
4476 (0.12), 4621 (23.4), 4688 (76.3)
ã
68 (0.4), 168 (0.07)
Ra x-rays 12 (8.4)
Ra226
1600y
Rn222
á
4602 (5.6), 4785 (94.4)
ã
186 (3.28)
Rn x-rays 12 (0.8), 81 (0.18), 84 (0.3), 95 (0.14)
61
Ra226
1600y
Rn222
á
4602 (5.6), 4785 (94.4)
ã
186 (3.28)
Rn x-rays 12 (0.8), 81 (0.18), 84 (0.3), 95 (0.14)
61
Progeny
Rn
222
kev and % abundance
is “radon” gas
Rn222
3.82d
Po218
á
ã
Progeny
kev and % abundance
Rn222 is “radon” gas
5490 (99.92), 4986 (0.08)
av. 512 (0.08)
Rn222
3.82d
Po218
á
ã
5490 (99.92), 4986 (0.08)
av. 512 (0.08)
Po218 decays 99.98 % of the time by á to Pb214 & 0.02 % of the
time by â- to At218
Po218 decays 99.98 % of the time by á to Pb214 & 0.02 % of the
time by â- to At218
Po218
3.05m
Pb214
At218
á
â-
6003 (99.98)
330 (0.02)
Po218
3.05m
Pb214
At218
á
â-
6003 (99.98)
330 (0.02)
At218
2s
Bi214
á-
6650 (6), 6700 (94)
At218
2s
Bi214
á-
6650 (6), 6700 (94)
Pb214
26.8m
Bi214
Pb214
26.8m
Bi214
â672 (48), 729 (42.5), 1024 (6.3)
ã
242 (7.49), 295 (19.2), 352 (37.2)
Bi x-rays 11 (13.5), 75 (6.2), 77 (10.5), 87 (4.7)
â672 (48), 729 (42.5), 1024 (6.3)
ã
242 (7.49), 295 (19.2), 352 (37.2)
Bi x-rays 11 (13.5), 75 (6.2), 77 (10.5), 87 (4.7)
Bi214 decays 99.979 % of the time by â- to Po214 & 0.021 % of
the time by á to Tl210
Bi214 decays 99.979 % of the time by â- to Po214 & 0.021 % of
the time by á to Tl210
Bi214
19.9m
Bi214
19.9m
Po214
Tl210
â1505 (17.7), 1540 (17.9), 3270 (17.2)
ã
609 (46.3), 1120 (15.1), 1764 (15.8)
Po x-rays 11 (0.5), 77 (0.36), 79 (0.6), 90 (0.3)
á
5450 (0.012), 5510 (0.008)
Po214
Tl210
â1505 (17.7), 1540 (17.9), 3270 (17.2)
ã
609 (46.3), 1120 (15.1), 1764 (15.8)
Po x-rays 11 (0.5), 77 (0.36), 79 (0.6), 90 (0.3)
á
5450 (0.012), 5510 (0.008)
62
Progeny
kev and % abundance
Rn222 is “radon” gas
Rn222
3.82d
Po218
62
á
ã
Progeny
kev and % abundance
Rn222 is “radon” gas
5490 (99.92), 4986 (0.08)
av. 512 (0.08)
Rn222
3.82d
Po218
á
ã
5490 (99.92), 4986 (0.08)
av. 512 (0.08)
Po218 decays 99.98 % of the time by á to Pb214 & 0.02 % of the
time by â- to At218
Po218 decays 99.98 % of the time by á to Pb214 & 0.02 % of the
time by â- to At218
Po218
3.05m
Pb214
At218
á
â-
6003 (99.98)
330 (0.02)
Po218
3.05m
Pb214
At218
á
â-
6003 (99.98)
330 (0.02)
At218
2s
Bi214
á-
6650 (6), 6700 (94)
At218
2s
Bi214
á-
6650 (6), 6700 (94)
Pb214
26.8m
Bi214
Pb214
26.8m
Bi214
â672 (48), 729 (42.5), 1024 (6.3)
ã
242 (7.49), 295 (19.2), 352 (37.2)
Bi x-rays 11 (13.5), 75 (6.2), 77 (10.5), 87 (4.7)
â672 (48), 729 (42.5), 1024 (6.3)
ã
242 (7.49), 295 (19.2), 352 (37.2)
Bi x-rays 11 (13.5), 75 (6.2), 77 (10.5), 87 (4.7)
Bi214 decays 99.979 % of the time by â- to Po214 & 0.021 % of
the time by á to Tl210
Bi214 decays 99.979 % of the time by â- to Po214 & 0.021 % of
the time by á to Tl210
Bi214
19.9m
Bi214
19.9m
Po214
Tl210
â1505 (17.7), 1540 (17.9), 3270 (17.2)
ã
609 (46.3), 1120 (15.1), 1764 (15.8)
Po x-rays 11 (0.5), 77 (0.36), 79 (0.6), 90 (0.3)
á
5450 (0.012), 5510 (0.008)
62
Po214
Tl210
â1505 (17.7), 1540 (17.9), 3270 (17.2)
ã
609 (46.3), 1120 (15.1), 1764 (15.8)
Po x-rays 11 (0.5), 77 (0.36), 79 (0.6), 90 (0.3)
á
5450 (0.012), 5510 (0.008)
62
Progeny
214
210
kev and % abundance
Po
164 ìs
Pb
á
ã
Tl210
1.30m
Pb210
Pb210
22.3 y
Bi210
7687 (99.989), 6892 (0.01)
797 (0.013
Progeny
kev and % abundance
Po214
164 ìs
Pb210
á
ã
â1320 (25), 1870 (56), 2340 (19)
ã
298 (79), 800 (99), 1310 (21)
Pb x-rays 11 (13), 73 (2.5), 75 (4.3), 85 (1.9)
Tl210
1.30m
Pb210
â1320 (25), 1870 (56), 2340 (19)
ã
298 (79), 800 (99), 1310 (21)
Pb x-rays 11 (13), 73 (2.5), 75 (4.3), 85 (1.9)
â17 (80.2), 63 (19.8)
ã
47 (4.05)
Bi x-rays 11 (24.3)
Pb210
22.3 y
Bi210
â17 (80.2), 63 (19.8)
ã
47 (4.05)
Bi x-rays 11 (24.3)
7687 (99.989), 6892 (0.01)
797 (0.013
Bi210 decays ~100 % of the time by â- to Po210 & 0.00013 % of
the time by á to Tl206
Bi210 decays ~100 % of the time by â- to Po210 & 0.00013 % of
the time by á to Tl206
Bi210
5.01d
Po210
Tl206
âá
1161 (99.9998)
4650 (0.00007), 4690 (0.00005)
Bi210
5.01d
Po210
Tl206
âá
1161 (99.9998)
4650 (0.00007), 4690 (0.00005)
Po210
Pb206
138.4d
á
5305 (99.9989)
Po210
Pb206
138.4d
á
5305 (99.9989)
Tl206
4.19m
â-
1520 (100)
Tl206
4.19m
â-
1520 (100)
Pb206
Pb206 is stable
Pb206
Pb206 is stable
63
Progeny
63
kev and % abundance
Po214
164 ìs
Pb210
á
ã
Tl210
1.30m
Pb210
Pb210
22.3 y
Bi210
7687 (99.989), 6892 (0.01)
797 (0.013
Progeny
kev and % abundance
Po214
164 ìs
Pb210
á
ã
â1320 (25), 1870 (56), 2340 (19)
ã
298 (79), 800 (99), 1310 (21)
Pb x-rays 11 (13), 73 (2.5), 75 (4.3), 85 (1.9)
Tl210
1.30m
Pb210
â1320 (25), 1870 (56), 2340 (19)
ã
298 (79), 800 (99), 1310 (21)
Pb x-rays 11 (13), 73 (2.5), 75 (4.3), 85 (1.9)
â17 (80.2), 63 (19.8)
ã
47 (4.05)
Bi x-rays 11 (24.3)
Pb210
22.3 y
Bi210
â17 (80.2), 63 (19.8)
ã
47 (4.05)
Bi x-rays 11 (24.3)
7687 (99.989), 6892 (0.01)
797 (0.013
Bi210 decays ~100 % of the time by â- to Po210 & 0.00013 % of
the time by á to Tl206
Bi210 decays ~100 % of the time by â- to Po210 & 0.00013 % of
the time by á to Tl206
Bi210
5.01d
Po210
Tl206
âá
1161 (99.9998)
4650 (0.00007), 4690 (0.00005)
Bi210
5.01d
Po210
Tl206
âá
1161 (99.9998)
4650 (0.00007), 4690 (0.00005)
Po210
Pb206
138.4d
á
5305 (99.9989)
Po210
Pb206
138.4d
á
5305 (99.9989)
Tl206
4.19m
â-
1520 (100)
Tl206
4.19m
â-
1520 (100)
Pb206
Pb206 is stable
Pb206
Pb206 is stable
63
63
SI and US “Traditional” Units
SI and US “Traditional” Units
Activity
1 TBq
=
1 GBq
=
1 Mbq
=
1 kBq
=
1 Bq
=
1 Bq
=
1 Bq
=
1 kCi
=
1 Ci
=
1 mCi
=
1 ìCi
=
1 nCi
=
1 nCi
=
1 nCi
=
1 pCi
=
1 pCi
=
27 Ci
27 mCi
27 ìCi
27 nCi
27 pCi
1 dps
60 dpm
37 TBq
37 Gbq
37 MBq
37 kBq
37 Bq
37 dps
2220 dpm
0.037 Bq
2.22 dpm
Absorbed Dose
1 kGy
=
100 krad
1 Gy
=
100 rad
1 mGy
=
100 mrad
1 ìGy
=
100 ìrad
1 krad
1 rad
1 mrad
1 ìrad
=
=
=
=
10 Gy
10 mGy
10 ìGy
10 nGy
Dose Equivalent
1 Sv
= 100 rem
1 mSv
= 100 mrem
1 mSv
= 0.10 rem
1 ìSv
= 100 ìrem
1 ìSv
= 0.10 mrem
1 nSv
= 0.10 ìrem
1 krem
1 rem
1 mrem
1 mrem
1 ìrem
1 ìrem
=
=
=
=
=
=
10 Sv
10 mSv
10 ìSv
0.01 mSv
0.01 ìSv
10 nSv
Dose Rate
1 Sv/h
= 100 rem/h
1 mSv/h = 100 mrem/h
1 mSv/h = 0.10 rem/h
1 ìSv/h = 100 ìrem/h
1 ìSv/h = 0.1 mrem/h
1 krem/h = 10 Sv/h
1 rem/h = 10 mSv/h
1 mrem/h = 10 ìSv/h
1 mrem/h = 0.01 mSv/h
1 ìrem/h = 0.01 ìSv/h
Activity
1 TBq
=
1 GBq
=
1 Mbq
=
1 kBq
=
1 Bq
=
1 Bq
=
1 Bq
=
1 kCi
=
1 Ci
=
1 mCi
=
1 ìCi
=
1 nCi
=
1 nCi
=
1 nCi
=
1 pCi
=
1 pCi
=
27 Ci
27 mCi
27 ìCi
27 nCi
27 pCi
1 dps
60 dpm
37 TBq
37 Gbq
37 MBq
37 kBq
37 Bq
37 dps
2220 dpm
0.037 Bq
2.22 dpm
Absorbed Dose
1 kGy
=
100 krad
1 Gy
=
100 rad
1 mGy
=
100 mrad
1 ìGy
=
100 ìrad
1 krad
1 rad
1 mrad
1 ìrad
=
=
=
=
10 Gy
10 mGy
10 ìGy
10 nGy
Absorbed Dose
1 kGy
=
100 krad
1 Gy
=
100 rad
1 mGy
=
100 mrad
1 ìGy
=
100 ìrad
1 krad
1 rad
1 mrad
1 ìrad
=
=
=
=
10 Gy
10 mGy
10 ìGy
10 nGy
64
=
=
=
=
=
=
10 Sv
10 mSv
10 ìSv
0.01 mSv
0.01 ìSv
10 nSv
Dose Rate
1 Sv/h
= 100 rem/h
1 mSv/h = 100 mrem/h
1 mSv/h = 0.10 rem/h
1 ìSv/h = 100 ìrem/h
1 ìSv/h = 0.1 mrem/h
1 krem/h = 10 Sv/h
1 rem/h = 10 mSv/h
1 mrem/h = 10 ìSv/h
1 mrem/h = 0.01 mSv/h
1 ìrem/h = 0.01 ìSv/h
SI and US “Traditional” Units
SI and US “Traditional” Units
27 Ci
27 mCi
27 ìCi
27 nCi
27 pCi
1 dps
60 dpm
37 TBq
37 Gbq
37 MBq
37 kBq
37 Bq
37 dps
2220 dpm
0.037 Bq
2.22 dpm
1 krem
1 rem
1 mrem
1 mrem
1 ìrem
1 ìrem
64
64
Activity
1 TBq
=
1 GBq
=
1 Mbq
=
1 kBq
=
1 Bq
=
1 Bq
=
1 Bq
=
1 kCi
=
1 Ci
=
1 mCi
=
1 ìCi
=
1 nCi
=
1 nCi
=
1 nCi
=
1 pCi
=
1 pCi
=
Dose Equivalent
1 Sv
= 100 rem
1 mSv
= 100 mrem
1 mSv
= 0.10 rem
1 ìSv
= 100 ìrem
1 ìSv
= 0.10 mrem
1 nSv
= 0.10 ìrem
Dose Equivalent
1 Sv
= 100 rem
1 mSv
= 100 mrem
1 mSv
= 0.10 rem
1 ìSv
= 100 ìrem
1 ìSv
= 0.10 mrem
1 nSv
= 0.10 ìrem
1 krem
1 rem
1 mrem
1 mrem
1 ìrem
1 ìrem
=
=
=
=
=
=
10 Sv
10 mSv
10 ìSv
0.01 mSv
0.01 ìSv
10 nSv
Dose Rate
1 Sv/h
= 100 rem/h
1 mSv/h = 100 mrem/h
1 mSv/h = 0.10 rem/h
1 ìSv/h = 100 ìrem/h
1 ìSv/h = 0.1 mrem/h
1 krem/h = 10 Sv/h
1 rem/h = 10 mSv/h
1 mrem/h = 10 ìSv/h
1 mrem/h = 0.01 mSv/h
1 ìrem/h = 0.01 ìSv/h
Activity
1 TBq
=
1 GBq
=
1 Mbq
=
1 kBq
=
1 Bq
=
1 Bq
=
1 Bq
=
1 kCi
=
1 Ci
=
1 mCi
=
1 ìCi
=
1 nCi
=
1 nCi
=
1 nCi
=
1 pCi
=
1 pCi
=
27 Ci
27 mCi
27 ìCi
27 nCi
27 pCi
1 dps
60 dpm
37 TBq
37 Gbq
37 MBq
37 kBq
37 Bq
37 dps
2220 dpm
0.037 Bq
2.22 dpm
Absorbed Dose
1 kGy
=
100 krad
1 Gy
=
100 rad
1 mGy
=
100 mrad
1 ìGy
=
100 ìrad
1 krad
1 rad
1 mrad
1 ìrad
=
=
=
=
10 Gy
10 mGy
10 ìGy
10 nGy
64
Dose Equivalent
1 Sv
= 100 rem
1 mSv
= 100 mrem
1 mSv
= 0.10 rem
1 ìSv
= 100 ìrem
1 ìSv
= 0.10 mrem
1 nSv
= 0.10 ìrem
1 krem
1 rem
1 mrem
1 mrem
1 ìrem
1 ìrem
=
=
=
=
=
=
10 Sv
10 mSv
10 ìSv
0.01 mSv
0.01 ìSv
10 nSv
Dose Rate
1 Sv/h
= 100 rem/h
1 mSv/h = 100 mrem/h
1 mSv/h = 0.10 rem/h
1 ìSv/h = 100 ìrem/h
1 ìSv/h = 0.1 mrem/h
1 krem/h = 10 Sv/h
1 rem/h = 10 mSv/h
1 mrem/h = 10 ìSv/h
1 mrem/h = 0.01 mSv/h
1 ìrem/h = 0.01 ìSv/h
ABBREVIATIONS
ampere
A, or amp
angstrom unit
A, or D
atmosphere
atm
atomic weight
at. wt.
becquerel
Bq
cubic foot
ft3, or cu ft
cubic feet per minute
ft3/min, or cfm
cubic inch
in3, or cu. in.
cubic meter
m3, or cu m
curie
Ci
day
day, or d
degree
deg, or 0
disintegrations per minute
dpm
foot
ft
gallon
gal
gallons per minute
gpm
gram
g or gm
hour
h, or hr
inch
in.
liter
liter, or L
meter
m
micron
ì, ìm, or mu
minute
min, or m
pounds per square inch
lb/in2, or psi
roentgen
R
second
sec, or s
square centimeter
cm2, or sq cm
square foot
ft2, sq ft
square meter
m2, or sq m
volt
V, or v
watt
W, or w
year
yr, or y
ABBREVIATIONS
ampere
A, or amp
angstrom unit
A, or D
atmosphere
atm
atomic weight
at. wt.
becquerel
Bq
cubic foot
ft3, or cu ft
cubic feet per minute
ft3/min, or cfm
cubic inch
in3, or cu. in.
cubic meter
m3, or cu m
curie
Ci
day
day, or d
degree
deg, or 0
disintegrations per minute
dpm
foot
ft
gallon
gal
gallons per minute
gpm
gram
g or gm
hour
h, or hr
inch
in.
liter
liter, or L
meter
m
micron
ì, ìm, or mu
minute
min, or m
pounds per square inch
lb/in2, or psi
roentgen
R
second
sec, or s
square centimeter
cm2, or sq cm
square foot
ft2, sq ft
square meter
m2, or sq m
volt
V, or v
watt
W, or w
year
yr, or y
ABBREVIATIONS
ampere
A, or amp
angstrom unit
A, or D
atmosphere
atm
atomic weight
at. wt.
becquerel
Bq
cubic foot
ft3, or cu ft
cubic feet per minute
ft3/min, or cfm
cubic inch
in3, or cu. in.
cubic meter
m3, or cu m
curie
Ci
day
day, or d
degree
deg, or 0
disintegrations per minute
dpm
foot
ft
gallon
gal
gallons per minute
gpm
gram
g or gm
hour
h, or hr
inch
in.
liter
liter, or L
meter
m
micron
ì, ìm, or mu
minute
min, or m
pounds per square inch
lb/in2, or psi
roentgen
R
second
sec, or s
square centimeter
cm2, or sq cm
square foot
ft2, sq ft
square meter
m2, or sq m
volt
V, or v
watt
W, or w
year
yr, or y
ABBREVIATIONS
ampere
A, or amp
angstrom unit
A, or D
atmosphere
atm
atomic weight
at. wt.
becquerel
Bq
cubic foot
ft3, or cu ft
cubic feet per minute
ft3/min, or cfm
cubic inch
in3, or cu. in.
cubic meter
m3, or cu m
curie
Ci
day
day, or d
degree
deg, or 0
disintegrations per minute
dpm
foot
ft
gallon
gal
gallons per minute
gpm
gram
g or gm
hour
h, or hr
inch
in.
liter
liter, or L
meter
m
micron
ì, ìm, or mu
minute
min, or m
pounds per square inch
lb/in2, or psi
roentgen
R
second
sec, or s
square centimeter
cm2, or sq cm
square foot
ft2, sq ft
square meter
m2, or sq m
volt
V, or v
watt
W, or w
year
yr, or y
CONVERSION OF UNITS
1 angstrom ( D) =
1 inch
=
1 meter
=
1 kilometer
=
1 mile
=
1 micron (ìm) =
1 mil
=
1 thousandth
=
of an inch (0.001")
1 yard
=
1 acre
1 barn
1 cm2
1 m2
1 m2
1 mile2
=
=
=
=
=
=
1 cm3 (cc)
1 cm3
1 cm3
1 ft3
1 ft3
1 liter
1 liter
1 liter
1 m3
1 m3
1 milliliter (ml)
=
=
=
=
=
=
=
=
=
=
=
Length
1E-8 cm
1 cm
2.54 cm
1 cm
3.2808 feet
1 foot
0.6214 miles
1 mile
5,280 feet
1 foot
1E-6 meters
1m
1E-3 inches
1 inch
2.54E-2 mm
1 mm
CONVERSION OF UNITS
=
=
=
=
=
=
=
=
1E8 D
0.3937 in
0.3048 m
1.609 km
1.894E-4 mile
1E6 ìm
1E3 mil
0.03937 in
0.9144 meters
1m
= 1.0936 yard
Area
43,560 ft2
1 ft2
= 2.296E-5 acre
1E-24 cm2
1 cm2 = 1E24 barn
0.1550 in2
1 in2
= 6.452 cm2
10.764 ft2
1 ft2
= 0.0929 m2
2
2
3.861E-7 mile
1 mile = 2.59E6 m2
640 acres
1 acre = 1.5625E-3 mile2
Volume
3.5315E-5 ft3
1 ft3
= 28,316 cm3
1E-6 m3
1 m3
= 1E6 cm3
0.03381 ounces 1 ounce = 29.58 cm3
28.316 liters
1 liter = 0.035315 ft3
7.481 gallons
1 gal = 0.1337 ft3
1.057 quarts
1 quart = 0.946 liter
0.2642 gallons
1 gal = 3.785 liter
61.0237 in3
1 in3
= 0.016387 liter
35.315 ft3
1 ft3
= 0.028316 m3
1,000 liters
1 liter = 1E-3 m3
1 cm3
1 cm3 = 1 ml
66
1 angstrom ( D) =
1 inch
=
1 meter
=
1 kilometer
=
1 mile
=
1 micron (ìm) =
1 mil
=
1 thousandth
=
of an inch (0.001")
1 yard
=
1 acre
1 barn
1 cm2
1 m2
1 m2
1 mile2
=
=
=
=
=
=
1 cm3 (cc)
1 cm3
1 cm3
1 ft3
1 ft3
1 liter
1 liter
1 liter
1 m3
1 m3
1 milliliter (ml)
=
=
=
=
=
=
=
=
=
=
=
CONVERSION OF UNITS
1 angstrom ( D) =
1 inch
=
1 meter
=
1 kilometer
=
1 mile
=
1 micron (ìm) =
1 mil
=
1 thousandth
=
of an inch (0.001")
1 yard
=
1 acre
1 barn
1 cm2
1 m2
1 m2
1 mile2
=
=
=
=
=
=
1 cm3 (cc)
1 cm3
1 cm3
1 ft3
1 ft3
1 liter
1 liter
1 liter
1 m3
1 m3
1 milliliter (ml)
=
=
=
=
=
=
=
=
=
=
=
Length
1E-8 cm
1 cm
2.54 cm
1 cm
3.2808 feet
1 foot
0.6214 miles
1 mile
5,280 feet
1 foot
1E-6 meters
1m
1E-3 inches
1 inch
2.54E-2 mm
1 mm
Length
1E-8 cm
1 cm
2.54 cm
1 cm
3.2808 feet
1 foot
0.6214 miles
1 mile
5,280 feet
1 foot
1E-6 meters
1m
1E-3 inches
1 inch
2.54E-2 mm
1 mm
=
=
=
=
=
=
=
=
1E8 D
0.3937 in
0.3048 m
1.609 km
1.894E-4 mile
1E6 ìm
1E3 mil
0.03937 in
0.9144 meters
1m
= 1.0936 yard
Area
43,560 ft2
1 ft2
= 2.296E-5 acre
2
1E-24 cm
1 cm2 = 1E24 barn
0.1550 in2
1 in2
= 6.452 cm2
2
2
10.764 ft
1 ft
= 0.0929 m2
2
2
3.861E-7 mile
1 mile = 2.59E6 m2
640 acres
1 acre = 1.5625E-3 mile2
Volume
3.5315E-5 ft3
1 ft3
= 28,316 cm3
3
3
1E-6 m
1m
= 1E6 cm3
0.03381 ounces 1 ounce = 29.58 cm3
28.316 liters
1 liter = 0.035315 ft3
7.481 gallons
1 gal = 0.1337 ft3
1.057 quarts
1 quart = 0.946 liter
0.2642 gallons
1 gal = 3.785 liter
61.0237 in3
1 in3
= 0.016387 liter
35.315 ft3
1 ft3
= 0.028316 m3
1,000 liters
1 liter = 1E-3 m3
1 cm3
1 cm3 = 1 ml
66
CONVERSION OF UNITS
=
=
=
=
=
=
=
=
1E8 D
0.3937 in
0.3048 m
1.609 km
1.894E-4 mile
1E6 ìm
1E3 mil
0.03937 in
0.9144 meters
1m
= 1.0936 yard
Area
43,560 ft2
1 ft2
= 2.296E-5 acre
1E-24 cm2
1 cm2 = 1E24 barn
0.1550 in2
1 in2
= 6.452 cm2
2
2
10.764 ft
1 ft
= 0.0929 m2
3.861E-7 mile2
1 mile2 = 2.59E6 m2
640 acres
1 acre = 1.5625E-3 mile2
Volume
3.5315E-5 ft3
1 ft3
= 28,316 cm3
3
3
1E-6 m
1m
= 1E6 cm3
0.03381 ounces 1 ounce = 29.58 cm3
28.316 liters
1 liter = 0.035315 ft3
7.481 gallons
1 gal = 0.1337 ft3
1.057 quarts
1 quart = 0.946 liter
0.2642 gallons
1 gal = 3.785 liter
61.0237 in3
1 in3
= 0.016387 liter
3
35.315 ft
1 ft3
= 0.028316 m3
1,000 liters
1 liter = 1E-3 m3
1 cm3
1 cm3 = 1 ml
1 angstrom ( D) =
1 inch
=
1 meter
=
1 kilometer
=
1 mile
=
1 micron (ìm) =
1 mil
=
1 thousandth
=
of an inch (0.001")
1 yard
=
1 acre
1 barn
1 cm2
1 m2
1 m2
1 mile2
=
=
=
=
=
=
1 cm3 (cc)
1 cm3
1 cm3
1 ft3
1 ft3
1 liter
1 liter
1 liter
1 m3
1 m3
1 milliliter (ml)
=
=
=
=
=
=
=
=
=
=
=
Length
1E-8 cm
1 cm
2.54 cm
1 cm
3.2808 feet
1 foot
0.6214 miles
1 mile
5,280 feet
1 foot
1E-6 meters
1m
1E-3 inches
1 inch
2.54E-2 mm
1 mm
=
=
=
=
=
=
=
=
1E8 D
0.3937 in
0.3048 m
1.609 km
1.894E-4 mile
1E6 ìm
1E3 mil
0.03937 in
0.9144 meters
1m
= 1.0936 yard
Area
43,560 ft2
1 ft2
= 2.296E-5 acre
1E-24 cm2
1 cm2 = 1E24 barn
0.1550 in2
1 in2
= 6.452 cm2
2
2
10.764 ft
1 ft
= 0.0929 m2
3.861E-7 mile2
1 mile2 = 2.59E6 m2
640 acres
1 acre = 1.5625E-3 mile2
Volume
3.5315E-5 ft3
1 ft3
= 28,316 cm3
3
3
1E-6 m
1m
= 1E6 cm3
0.03381 ounces 1 ounce = 29.58 cm3
28.316 liters
1 liter = 0.035315 ft3
7.481 gallons
1 gal = 0.1337 ft3
1.057 quarts
1 quart = 0.946 liter
0.2642 gallons
1 gal = 3.785 liter
61.0237 in3
1 in3
= 0.016387 liter
3
35.315 ft
1 ft3
= 0.028316 m3
1,000 liters
1 liter = 1E-3 m3
3
1 cm
1 cm3 = 1 ml
1 gram
1 kilogram
1 pound
1 pound
=
=
=
=
Mass
0.03527 ounces
2.2046 pounds
16 ounces
453.59 grams
1 ounce
1 lbs
1 ounce
1 gram
Density
1 gram / cm3 = 62.428 lbs / ft3
1 lb/ft3
3
1 gram / cm = 8.345 lbs / gal
1 lb/gal
1 Bq / M3
1 Bq / M3
1 pCi / L
1 ìCi / cc
1 DPM / M3
1 ìCi / cc
1 Bq / M3
1 pCi / ft3
1 ìCi / cc
=
=
=
=
=
=
=
=
=
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 bar
=
1 dyne/cm2 =
1 Torr
=
1 dyne/cm2 =
1 gram
1 kilogram
1 pound
1 pound
=
=
=
=
=
=
=
=
=
=
=
=
=
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 bar
=
1 dyne/cm2 =
1 Torr
=
1 dyne/cm2 =
28.35 g
0.4536 kg
0.0625 lb
2.2046E-3 lb
= 0.016018 g/cm3
= 0.1198 g/cm3
Concentration
60 DPM / M3
1 DPM/M3 = 0.0167 Bq/M3
0.027027pCi/L
1 pCi / L = 37 Bq / M3
1E-9 ìCi / cc
1 ìCi / cc = 1E9 pCi / L
2.22E12 DPM/M3
4.5045E-13ìCi/cc
3.7E10 Bq / M3
2.7027E-11 ìCi/cc
3.5315E-11 ìCi / cc
2.8316E10 pCi / ft3
Pressure
1.01325 bars
1 bar
= 0.9869 atm
101.325 kPa
1 kPa
= 0.009869 atm
14.696 lbs / in2
1 lbs / in2 = 0.06805 atm
760 mm Hg
1 mm Hg = 0.001316 atm
29.9213 “Hg
1 “Hg
= 0.033421 atm
33.8995 feet H2O 1 ft H2O = 0.0295 atm
1E6 dynes / cm2 1 dyne/cm2 = 1E-6 bar
0.1 Pascals
1 Pascal = 10 dyne/cm2
1 mm Hg
1 mm Hg = 1 Torr
1.0197E-3 g/cm2 1 g/cm2 = 980.68 dyne/cm2
67
Mass
0.03527 ounces
2.2046 pounds
16 ounces
453.59 grams
1 ounce
1 lbs
1 ounce
1 gram
Density
1 gram / cm3 = 62.428 lbs / ft3
1 lb/ft3
1 gram / cm3 = 8.345 lbs / gal
1 lb/gal
1 Bq / M3
1 Bq / M3
1 pCi / L
1 ìCi / cc
1 DPM / M3
1 ìCi / cc
1 Bq / M3
1 pCi / ft3
1 ìCi / cc
=
=
=
=
=
=
=
=
28.35 g
0.4536 kg
0.0625 lb
2.2046E-3 lb
= 0.016018 g/cm3
= 0.1198 g/cm3
1 gram
1 kilogram
1 pound
1 pound
=
=
=
=
Mass
0.03527 ounces
2.2046 pounds
16 ounces
453.59 grams
1 ounce
1 lbs
1 ounce
1 gram
Density
1 gram / cm3 = 62.428 lbs / ft3
1 lb/ft3
1 gram / cm3 = 8.345 lbs / gal
1 lb/gal
1 Bq / M3
1 Bq / M3
1 pCi / L
1 ìCi / cc
1 DPM / M3
1 ìCi / cc
1 Bq / M3
1 pCi / ft3
1 ìCi / cc
=
=
=
=
=
=
=
=
=
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 bar
=
1 dyne/cm2 =
1 Torr
=
1 dyne/cm2 =
1 gram
1 kilogram
1 pound
1 pound
=
=
=
=
1 Bq / M3
1 Bq / M3
1 pCi / L
1 ìCi / cc
1 DPM / M3
1 ìCi / cc
1 Bq / M3
1 pCi / ft3
1 ìCi / cc
Pressure
1.01325 bars
1 bar
= 0.9869 atm
101.325 kPa
1 kPa
= 0.009869 atm
14.696 lbs / in2
1 lbs / in2 = 0.06805 atm
760 mm Hg
1 mm Hg = 0.001316 atm
29.9213 “Hg
1 “Hg
= 0.033421 atm
33.8995 feet H2O 1 ft H2O = 0.0295 atm
1E6 dynes / cm2 1 dyne/cm2 = 1E-6 bar
0.1 Pascals
1 Pascal = 10 dyne/cm2
1 mm Hg
1 mm Hg = 1 Torr
1.0197E-3 g/cm2 1 g/cm2 = 980.68 dyne/cm2
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 atmosphere =
1 bar
=
1 dyne/cm2 =
1 Torr
=
1 dyne/cm2 =
=
=
=
=
=
=
=
=
=
28.35 g
0.4536 kg
0.0625 lb
2.2046E-3 lb
= 0.016018 g/cm3
= 0.1198 g/cm3
Concentration
60 DPM / M3
1 DPM/M3 = 0.0167 Bq/M3
0.027027pCi/L
1 pCi / L = 37 Bq / M3
1E-9 ìCi / cc
1 ìCi / cc = 1E9 pCi / L
2.22E12 DPM/M3
4.5045E-13ìCi/cc
3.7E10 Bq / M3
2.7027E-11 ìCi/cc
3.5315E-11 ìCi / cc
2.8316E10 pCi / ft3
Pressure
1.01325 bars
1 bar
= 0.9869 atm
101.325 kPa
1 kPa
= 0.009869 atm
14.696 lbs / in2
1 lbs / in2 = 0.06805 atm
760 mm Hg
1 mm Hg = 0.001316 atm
29.9213 “Hg
1 “Hg
= 0.033421 atm
33.8995 feet H2 O 1 ft H2 O = 0.0295 atm
1E6 dynes / cm2 1 dyne/cm2 = 1E-6 bar
0.1 Pascals
1 Pascal = 10 dyne/cm2
1 mm Hg
1 mm Hg = 1 Torr
1.0197E-3 g/cm2 1 g/cm2 = 980.68 dyne/cm2
67
Mass
0.03527 ounces
2.2046 pounds
16 ounces
453.59 grams
1 ounce
1 lbs
1 ounce
1 gram
Density
1 gram / cm3 = 62.428 lbs / ft3
1 lb/ft3
1 gram / cm3 = 8.345 lbs / gal
1 lb/gal
Concentration
60 DPM / M3
1 DPM/M3 = 0.0167 Bq/M3
0.027027pCi/L
1 pCi / L = 37 Bq / M3
1E-9 ìCi / cc
1 ìCi / cc = 1E9 pCi / L
2.22E12 DPM/M3
4.5045E-13ìCi/cc
3.7E10 Bq / M3
2.7027E-11 ìCi/cc
3.5315E-11 ìCi / cc
2.8316E10 pCi / ft3
=
=
=
=
=
=
=
=
28.35 g
0.4536 kg
0.0625 lb
2.2046E-3 lb
= 0.016018 g/cm3
= 0.1198 g/cm3
Concentration
60 DPM / M3
1 DPM/M3 = 0.0167 Bq/M3
0.027027pCi/L
1 pCi / L = 37 Bq / M3
1E-9 ìCi / cc
1 ìCi / cc = 1E9 pCi / L
2.22E12 DPM/M3
4.5045E-13ìCi/cc
3.7E10 Bq / M3
2.7027E-11 ìCi/cc
3.5315E-11 ìCi / cc
2.8316E10 pCi / ft3
Pressure
1.01325 bars
1 bar
= 0.9869 atm
101.325 kPa
1 kPa
= 0.009869 atm
14.696 lbs / in2
1 lbs / in2 = 0.06805 atm
760 mm Hg
1 mm Hg = 0.001316 atm
29.9213 “Hg
1 “Hg
= 0.033421 atm
33.8995 feet H2 O 1 ft H2 O = 0.0295 atm
1E6 dynes / cm2 1 dyne/cm2 = 1E-6 bar
0.1 Pascals
1 Pascal = 10 dyne/cm2
1 mm Hg
1 mm Hg = 1 Torr
1.0197E-3 g/cm2 1 g/cm2 = 980.68 dyne/cm2
1 rad
1 erg / g
1 rad
1 eV / g
1 roentgen
1 erg / g of air
1 roentgen
1 ion pair / g of air
1 roentgen
1 eV / g of air
1 roentgen
1 rad (in soft tissue)
1 rem
1 erg /g in tissue
1 sievert (Sv)
1 rem
1 sievert
1 curie (Ci)
1 dps
1 curie
1 dpm
1 ìCi / m2
1 dpm / cm2
1 megaCi / sq mile
1 Ci / m2
1 dpm / m3
1 ìCi / cm3
1 becquerel (Bq)
1 Ci
1 becquerel
1 dps
1 rad
1 erg / g
1 rad
1 eV / g
1 roentgen
1 erg / g of air
1 roentgen
1 ion pair / g of air
1 roentgen
1 eV / g of air
1 roentgen
1 rad (in soft tissue)
1 rem
1 erg /g in tissue
1 sievert (Sv)
1 rem
1 sievert
1 curie (Ci)
1 dps
1 curie
1 dpm
1 ìCi / m2
1 dpm / cm2
1 megaCi / sq mile
1 Ci / m2
1 dpm / m3
1 ìCi / cm3
1 becquerel (Bq)
1 Ci
1 becquerel
1 dps
Radiological
=
100 ergs / g
=
0.01 rad
=
6.242E13 eV / g
=
1.602E-13 roentgen
=
87.7 ergs / g of air
=
0.0114 roentgen
=
1.61E12 ion pairs/g of air
=
6.21E-13 roentgen
=
5.47E13 eV / g of air
=
1.828E-14 roentgen
=
0.98 rads (in soft tissue)
=
1.02 roentgen
=
100 ergs / g in tissue
=
0.01 rem
=
100 rem
=
0.01 Sv
=
1 J / kg
=
3.7E10 dps
=
2.7027E-11 Ci
=
2.22E12 dpm
=
4.5045E-13 Ci
=
222 dpm / cm2
=
0.0045 ìCi / m2
=
0.386 Ci / m2
=
2.59 megaCi/sq mile
=
4.5E-13 ìCi / cm3
=
2.22E12 dpm / m3
=
2.7027E-11 Ci
=
3.7E10 Bq
=
1 dps
=
1 Bq
68
Radiological
=
100 ergs / g
=
0.01 rad
=
6.242E13 eV / g
=
1.602E-13 roentgen
=
87.7 ergs / g of air
=
0.0114 roentgen
=
1.61E12 ion pairs/g of air
=
6.21E-13 roentgen
=
5.47E13 eV / g of air
=
1.828E-14 roentgen
=
0.98 rads (in soft tissue)
=
1.02 roentgen
=
100 ergs / g in tissue
=
0.01 rem
=
100 rem
=
0.01 Sv
=
1 J / kg
=
3.7E10 dps
=
2.7027E-11 Ci
=
2.22E12 dpm
=
4.5045E-13 Ci
=
222 dpm / cm2
=
0.0045 ìCi / m2
=
0.386 Ci / m2
=
2.59 megaCi/sq mile
=
4.5E-13 ìCi / cm3
=
2.22E12 dpm / m3
=
2.7027E-11 Ci
=
3.7E10 Bq
=
1 dps
=
1 Bq
1 rad
1 erg / g
1 rad
1 eV / g
1 roentgen
1 erg / g of air
1 roentgen
1 ion pair / g of air
1 roentgen
1 eV / g of air
1 roentgen
1 rad (in soft tissue)
1 rem
1 erg /g in tissue
1 sievert (Sv)
1 rem
1 sievert
1 curie (Ci)
1 dps
1 curie
1 dpm
1 ìCi / m2
1 dpm / cm2
1 megaCi / sq mile
1 Ci / m2
1 dpm / m3
1 ìCi / cm3
1 becquerel (Bq)
1 Ci
1 becquerel
1 dps
Radiological
=
100 ergs / g
=
0.01 rad
=
6.242E13 eV / g
=
1.602E-13 roentgen
=
87.7 ergs / g of air
=
0.0114 roentgen
=
1.61E12 ion pairs/g of air
=
6.21E-13 roentgen
=
5.47E13 eV / g of air
=
1.828E-14 roentgen
=
0.98 rads (in soft tissue)
=
1.02 roentgen
=
100 ergs / g in tissue
=
0.01 rem
=
100 rem
=
0.01 Sv
=
1 J / kg
=
3.7E10 dps
=
2.7027E-11 Ci
=
2.22E12 dpm
=
4.5045E-13 Ci
=
222 dpm / cm2
=
0.0045 ìCi / m2
=
0.386 Ci / m2
=
2.59 megaCi/sq mile
=
4.5E-13 ìCi / cm3
=
2.22E12 dpm / m3
=
2.7027E-11 Ci
=
3.7E10 Bq
=
1 dps
=
1 Bq
68
1 rad
1 erg / g
1 rad
1 eV / g
1 roentgen
1 erg / g of air
1 roentgen
1 ion pair / g of air
1 roentgen
1 eV / g of air
1 roentgen
1 rad (in soft tissue)
1 rem
1 erg /g in tissue
1 sievert (Sv)
1 rem
1 sievert
1 curie (Ci)
1 dps
1 curie
1 dpm
1 ìCi / m2
1 dpm / cm2
1 megaCi / sq mile
1 Ci / m2
1 dpm / m3
1 ìCi / cm3
1 becquerel (Bq)
1 Ci
1 becquerel
1 dps
Radiological
=
100 ergs / g
=
0.01 rad
=
6.242E13 eV / g
=
1.602E-13 roentgen
=
87.7 ergs / g of air
=
0.0114 roentgen
=
1.61E12 ion pairs/g of air
=
6.21E-13 roentgen
=
5.47E13 eV / g of air
=
1.828E-14 roentgen
=
0.98 rads (in soft tissue)
=
1.02 roentgen
=
100 ergs / g in tissue
=
0.01 rem
=
100 rem
=
0.01 Sv
=
1 J / kg
=
3.7E10 dps
=
2.7027E-11 Ci
=
2.22E12 dpm
=
4.5045E-13 Ci
=
222 dpm / cm2
=
0.0045 ìCi / m2
=
0.386 Ci / m2
=
2.59 megaCi/sq mile
=
4.5E-13 ìCi / cm3
=
2.22E12 dpm / m3
=
2.7027E-11 Ci
=
3.7E10 Bq
=
1 dps
=
1 Bq
118
Radiological
=
1.28E-8 g 235U fissioned
=
7.81E7 BTU
=
3.29E13 fissions
=
3.04E-14 BTU
=
1 megawatt-days
=
1 g 235U fissioned
=
1.8E-2 kilotons TNT
=
55.6 g 235U fissioned
=
8.9058E-18 kW-hours
=
1.123E17 fissions
=
3.204E-4 ergs
=
3.121E3 fissions
=
6.9E-21 Megatons TNT
=
1.45E20 fissions
=
100 rads
=
0.01 gray
=
6.24E18 eV
=
1.602E-19 joule
1 BTU
1 g 235U fissioned
1 BTU
1 fission
1 g 235U fissioned
1 MW-days
1 g 235U fissioned
1 kilotons TNT
1 fission
1 kW-hrs
1 fission
1 erg
1 fission
1 Megatons TNT
1 gray
1 rad
1 joule (J)
1 eV
1 ampere
3.336E-10 amp
1 ampere
1.602E-19 amp
1 coulomb
1 electronic charge
=
=
=
=
=
=
Others
2.998 E9 electrostatic units/sec
1 electrostatic unit/sec
6.242 E18 electronic charges/sec
1 electronic charge/sec
6.242 E18 electronic charges
1.602E-19 coulomb
Radiological
=
1.28E-8 g 235U fissioned
=
7.81E7 BTU
=
3.29E13 fissions
=
3.04E-14 BTU
=
1 megawatt-days
=
1 g 235U fissioned
=
1.8E-2 kilotons TNT
=
55.6 g 235U fissioned
=
8.9058E-18 kW-hours
=
1.123E17 fissions
=
3.204E-4 ergs
=
3.121E3 fissions
=
6.9E-21 Megatons TNT
=
1.45E20 fissions
=
100 rads
=
0.01 gray
=
6.24E18 eV
=
1.602E-19 joule
1 BTU
1 g 235U fissioned
1 BTU
1 fission
1 g 235U fissioned
1 MW-days
1 g 235U fissioned
1 kilotons TNT
1 fission
1 kW-hrs
1 fission
1 erg
1 fission
1 Megatons TNT
1 gray
1 rad
1 joule (J)
1 eV
1 ampere
3.336E-10 amp
1 ampere
1.602E-19 amp
1 coulomb
1 electronic charge
=
=
=
=
=
=
69
Radiological
=
1.28E-8 g 235U fissioned
=
7.81E7 BTU
=
3.29E13 fissions
=
3.04E-14 BTU
=
1 megawatt-days
=
1 g 235U fissioned
=
1.8E-2 kilotons TNT
=
55.6 g 235U fissioned
=
8.9058E-18 kW-hours
=
1.123E17 fissions
=
3.204E-4 ergs
=
3.121E3 fissions
=
6.9E-21 Megatons TNT
=
1.45E20 fissions
=
100 rads
=
0.01 gray
=
6.24E18 eV
=
1.602E-19 joule
1 BTU
1 g 235U fissioned
1 BTU
1 fission
1 g 235U fissioned
1 MW-days
1 g 235U fissioned
1 kilotons TNT
1 fission
1 kW-hrs
1 fission
1 erg
1 fission
1 Megatons TNT
1 gray
1 rad
1 joule (J)
1 eV
1 ampere
3.336E-10 amp
1 ampere
1.602E-19 amp
1 coulomb
1 electronic charge
=
=
=
=
=
=
Others
2.998 E9 electrostatic units/sec
1 electrostatic unit/sec
6.242 E18 electronic charges/sec
1 electronic charge/sec
6.242 E18 electronic charges
1.602E-19 coulomb
119
Others
2.998 E9 electrostatic units/sec
1 electrostatic unit/sec
6.242 E18 electronic charges/sec
1 electronic charge/sec
6.242 E18 electronic charges
1.602E-19 coulomb
69
Radiological
=
1.28E-8 g 235U fissioned
=
7.81E7 BTU
=
3.29E13 fissions
=
3.04E-14 BTU
=
1 megawatt-days
=
1 g 235U fissioned
=
1.8E-2 kilotons TNT
=
55.6 g 235U fissioned
=
8.9058E-18 kW-hours
=
1.123E17 fissions
=
3.204E-4 ergs
=
3.121E3 fissions
=
6.9E-21 Megatons TNT
=
1.45E20 fissions
=
100 rads
=
0.01 gray
=
6.24E18 eV
=
1.602E-19 joule
1 BTU
1 g 235U fissioned
1 BTU
1 fission
1 g 235U fissioned
1 MW-days
1 g 235U fissioned
1 kilotons TNT
1 fission
1 kW-hrs
1 fission
1 erg
1 fission
1 Megatons TNT
1 gray
1 rad
1 joule (J)
1 eV
1 ampere
3.336E-10 amp
1 ampere
1.602E-19 amp
1 coulomb
1 electronic charge
=
=
=
=
=
=
Others
2.998 E9 electrostatic units/sec
1 electrostatic unit/sec
6.242 E18 electronic charges/sec
1 electronic charge/sec
6.242 E18 electronic charges
1.602E-19 coulomb
Power
1E7 ergs/sec
1 erg/sec
1E7 ergs/sec
1 erg/sec
1 joule/sec
1 joule/sec
0.001341 hp
1 hp
0.01757 kW
1 kW
0.023575 hp
1 hp
9.478E-4 BTU 1 BTU
1E7 ergs
1 erg
0.003971 BTU 1 BTU
1 joule/sec
1 watt
1 watt
1 watt
1 BTU/min
1 BTU/min
1 joule
1 joule
1 calorie, g
=
=
=
=
=
=
=
=
=
1E18
1E15
1E12
1E9
1E6
1E3
Exa
Peta
tera
giga
mega
kilo
MULTIPLES AND SUBMULTIPLES
E
1E2 hecto
h 1E-6
micro
P
1E1 deka
da 1E-9
nano
T
1E0 1
1 1E-12 pico
G
1E-1 deci
d 1E-15 femto
M
1E-2 centi
c 1E-18 atto
k
1E-3 milli
m
A
B
G
D
E
Z
H
Q
Alpha
Beta
Gamma
Delta
Epsilon
Zeta
Eta
Theta
á
$
(
*
,
.
ç
è
GREEK ALPHABET
I é
Iota
R
K 6
Kappa
S
L ë
Lambda
T
Ìì
Mu
U
N <
Nu
F
X >
Xi
C
O @
Omicron
Y
P ð
Pi
Ù
= 1E-7 joule/sec
= 1E-7 watt
= 1 watt
= 745.7 watts
= 56.9 BTU/min
= 42.4 BTU/min
= 1.055E3 joules
= 1E-7 joule
= 251.8 calories, g
ñ
ó
ô
L
ö
÷
ø
ù
ì
n
p
f
a
Rho
Sigma
Tau
Upsilon
Phi
Chi
Psi
Omega
=
=
=
=
=
=
=
=
=
1E18
1E15
1E12
1E9
1E6
1E3
Exa
Peta
tera
giga
mega
kilo
MULTIPLES AND SUBMULTIPLES
E
1E2 hecto
h 1E-6
micro
P
1E1 deka
da 1E-9
nano
T
1E0 1
1 1E-12 pico
G
1E-1 deci
d 1E-15 femto
M
1E-2 centi
c 1E-18 atto
k
1E-3 milli
m
A
B
G
D
E
Z
H
Q
Alpha
Beta
Gamma
Delta
Epsilon
Zeta
Eta
Theta
á
$
(
*
,
.
ç
è
70
Power
1E7 ergs/sec
1 erg/sec
1E7 ergs/sec
1 erg/sec
1 joule/sec
1 joule/sec
0.001341 hp
1 hp
0.01757 kW
1 kW
0.023575 hp
1 hp
9.478E-4 BTU 1 BTU
1E7 ergs
1 erg
0.003971 BTU 1 BTU
=
=
=
=
=
=
=
=
=
1E18
1E15
1E12
1E9
1E6
1E3
Exa
Peta
tera
giga
mega
kilo
MULTIPLES AND SUBMULTIPLES
E
1E2 hecto
h 1E-6
micro
P
1E1 deka
da 1E-9
nano
T
1E0 1
1 1E-12 pico
G
1E-1 deci
d 1E-15 femto
M
1E-2 centi
c 1E-18 atto
k
1E-3 milli
m
A
B
G
D
E
Z
H
Q
Alpha
Beta
Gamma
Delta
Epsilon
Zeta
Eta
Theta
GREEK ALPHABET
I é
Iota
R
K 6
Kappa
S
L ë
Lambda
T
Ìì
Mu
U
N <
Nu
F
X >
Xi
C
O @
Omicron
Y
P ð
Pi
Ù
70
GREEK ALPHABET
I é
Iota
R
K 6
Kappa
S
L ë
Lambda
T
Ìì
Mu
U
N <
Nu
F
X >
Xi
C
O @
Omicron
Y
P ð
Pi
Ù
= 1E-7 joule/sec
= 1E-7 watt
= 1 watt
= 745.7 watts
= 56.9 BTU/min
= 42.4 BTU/min
= 1.055E3 joules
= 1E-7 joule
= 251.8 calories, g
ñ
ó
ô
L
ö
÷
ø
ù
ì
n
p
f
a
Rho
Sigma
Tau
Upsilon
Phi
Chi
Psi
Omega
70
1 joule/sec
1 watt
1 watt
1 watt
1 BTU/min
1 BTU/min
1 joule
1 joule
1 calorie, g
á
$
(
*
,
.
ç
è
Power
1E7 ergs/sec
1 erg/sec
1E7 ergs/sec
1 erg/sec
1 joule/sec
1 joule/sec
0.001341 hp
1 hp
0.01757 kW
1 kW
0.023575 hp
1 hp
9.478E-4 BTU 1 BTU
1E7 ergs
1 erg
0.003971 BTU 1 BTU
1 joule/sec
1 watt
1 watt
1 watt
1 BTU/min
1 BTU/min
1 joule
1 joule
1 calorie, g
= 1E-7 joule/sec
= 1E-7 watt
= 1 watt
= 745.7 watts
= 56.9 BTU/min
= 42.4 BTU/min
= 1.055E3 joules
= 1E-7 joule
= 251.8 calories, g
ñ
ó
ô
L
ö
÷
ø
ù
ì
n
p
f
a
Rho
Sigma
Tau
Upsilon
Phi
Chi
Psi
Omega
Power
1E7 ergs/sec
1 erg/sec
1E7 ergs/sec
1 erg/sec
1 joule/sec
1 joule/sec
0.001341 hp
1 hp
0.01757 kW
1 kW
0.023575 hp
1 hp
9.478E-4 BTU 1 BTU
1E7 ergs
1 erg
0.003971 BTU 1 BTU
1 joule/sec
1 watt
1 watt
1 watt
1 BTU/min
1 BTU/min
1 joule
1 joule
1 calorie, g
=
=
=
=
=
=
=
=
=
1E18
1E15
1E12
1E9
1E6
1E3
Exa
Peta
tera
giga
mega
kilo
MULTIPLES AND SUBMULTIPLES
E
1E2 hecto
h 1E-6
micro
P
1E1 deka
da 1E-9
nano
T
1E0 1
1 1E-12 pico
G
1E-1 deci
d 1E-15 femto
M
1E-2 centi
c 1E-18 atto
k
1E-3 milli
m
A
B
G
D
E
Z
H
Q
Alpha
Beta
Gamma
Delta
Epsilon
Zeta
Eta
Theta
á
$
(
*
,
.
ç
è
GREEK ALPHABET
I é
Iota
R
K 6
Kappa
S
L ë
Lambda
T
Ìì
Mu
U
N <
Nu
F
X >
Xi
C
O @
Omicron
Y
P ð
Pi
Ù
70
= 1E-7 joule/sec
= 1E-7 watt
= 1 watt
= 745.7 watts
= 56.9 BTU/min
= 42.4 BTU/min
= 1.055E3 joules
= 1E-7 joule
= 251.8 calories, g
ñ
ó
ô
L
ö
÷
ø
ù
ì
n
p
f
a
Rho
Sigma
Tau
Upsilon
Phi
Chi
Psi
Omega
CONSTANTS
Avogadro's number (N0 )
6.02252E23
electron charge (e)
4.80298E-10 esu
electron rest mass (me)
9.1091 E-28 g
acceleration of gravity (g)
32.1725 ft / sec2
0
@ sea level & 45 latitude
980.621 cm / sec2
Planck's constant (h)
6.625E-27 erg-sec
velocity of light (c)
2.9979E10 cm / sec
186,280 miles / sec
ideal gas volume (V0)
22,414 cm3 / mole (STP)
neutron mass
1.67482E-24 g
proton mass
1.67252E-24 g
ratio of proton to electron mass
1836.13
natural base of logarithms (e)
2.71828
p
3.14159
1C
6.2418E18 esus
1A
1 C/sec
1 barn (b)
1E-24 cm2
-1
charge (e )
1.6E-19 C
W for air
33.8 eV / ion pair
Universal gas constant (R)
8.32E7 ergs/0C gram mol
A gram-molecular weight of any gas contains Avogadro's
number, N0 (6.02252 E23) atoms and occupies a volume of
22,414 cm3 at STP.
CONSTANTS
Avogadro's number (N0)
6.02252E23
electron charge (e)
4.80298E-10 esu
electron rest mass (me)
9.1091 E-28 g
acceleration of gravity (g)
32.1725 ft / sec2
@ sea level & 450 latitude
980.621 cm / sec2
Planck's constant (h)
6.625E-27 erg-sec
velocity of light (c)
2.9979E10 cm / sec
186,280 miles / sec
ideal gas volume (V0)
22,414 cm3 / mole (STP)
neutron mass
1.67482E-24 g
proton mass
1.67252E-24 g
ratio of proton to electron mass
1836.13
natural base of logarithms (e)
2.71828
p
3.14159
1C
6.2418E18 esus
1A
1 C/sec
1 barn (b)
1E-24 cm2
-1
charge (e )
1.6E-19 C
W for air
33.8 eV / ion pair
Universal gas constant (R)
8.32E7 ergs/0C gram mol
A gram-molecular weight of any gas contains Avogadro's
number, N0 (6.02252 E23) atoms and occupies a volume of
22,414 cm3 at STP.
Temperature
0
C = (0F - 32)(5/9)
0
K = 0C + 273.1
0
0
F = 0C x 1.8 + 32
R = 0F + 459.58
Temperature
0
C = (0F - 32)(5/9)
0
K = 0C + 273.1
0
0
F = 0C x 1.8 + 32
R = 0F + 459.58
71
71
CONSTANTS
Avogadro's number (N0 )
6.02252E23
electron charge (e)
4.80298E-10 esu
electron rest mass (me)
9.1091 E-28 g
acceleration of gravity (g)
32.1725 ft / sec2
@ sea level & 450 latitude
980.621 cm / sec2
Planck's constant (h)
6.625E-27 erg-sec
velocity of light (c)
2.9979E10 cm / sec
186,280 miles / sec
ideal gas volume (V0)
22,414 cm3 / mole (STP)
neutron mass
1.67482E-24 g
proton mass
1.67252E-24 g
ratio of proton to electron mass
1836.13
natural base of logarithms (e)
2.71828
p
3.14159
1C
6.2418E18 esus
1A
1 C/sec
1 barn (b)
1E-24 cm2
charge (e-1)
1.6E-19 C
W for air
33.8 eV / ion pair
Universal gas constant (R)
8.32E7 ergs/0C gram mol
A gram-molecular weight of any gas contains Avogadro's
number, N0 (6.02252 E23) atoms and occupies a volume of
22,414 cm3 at STP.
CONSTANTS
Avogadro's number (N0)
6.02252E23
electron charge (e)
4.80298E-10 esu
electron rest mass (me)
9.1091 E-28 g
acceleration of gravity (g)
32.1725 ft / sec2
@ sea level & 450 latitude
980.621 cm / sec2
Planck's constant (h)
6.625E-27 erg-sec
velocity of light (c)
2.9979E10 cm / sec
186,280 miles / sec
ideal gas volume (V0)
22,414 cm3 / mole (STP)
neutron mass
1.67482E-24 g
proton mass
1.67252E-24 g
ratio of proton to electron mass
1836.13
natural base of logarithms (e)
2.71828
p
3.14159
1C
6.2418E18 esus
1A
1 C/sec
1 barn (b)
1E-24 cm2
-1
charge (e )
1.6E-19 C
W for air
33.8 eV / ion pair
Universal gas constant (R)
8.32E7 ergs/0C gram mol
A gram-molecular weight of any gas contains Avogadro's
number, N0 (6.02252 E23) atoms and occupies a volume of
22,414 cm3 at STP.
Temperature
0
C = (0F - 32)(5/9)
0
K = 0C + 273.1
0
F = 0C x 1.8 + 32
0
R = 0F + 459.58
71
Temperature
0
C = (0F - 32)(5/9)
0
K = 0C + 273.1
0
0
71
F = 0C x 1.8 + 32
R = 0F + 459.58
UNITS AND TERMINOLOGY
“Special Units”
SI Units
Exposure
Roentgen
Coulombs / kg
Dose
rad (0.01 Gy)
Gray (100 rad)
Dose Equiv
rem (0.01 Sv)
Sievert (100 rem)
Activity
Curie (2.22 E12 dpm)
Becquerel (1dps)
1 Roentgen
= 2.58 E-4 coulomb / kg in air
= 1 esu / cm3 in air
= 87.7 ergs / gm in air
= 98 ergs / gm in soft tissue
1 rad
= 100 ergs / gm in any absorber
1 Gray
= 10,000 ergs / gm in any absorber
1 rem
= 1 rad x QF
= 0.01 Sv
H
= DQN (from ICRP 26)
H (Dose Equiv.)
= D (absorbed dose) x Q (quality factor)
x N (any other modifying factors)
Acute
Chronic
Somatic
Genetic
Teratogenic
Stochastic
Non-Stochastic
(deterministic)
DEFINITIONS
any dose in a short period of time
any dose in a long period of time
effects in the exposed individual
effects in the offspring of the exposed
individual
effects in the exposed unborn embryo/fetus
effects for which a probability exists and
increases with increasing dose
effects for which a threshold exists effects do not occur below the threshold
(examples; cataracts, erythema, epilation,
acute radiation syndrome)
UNITS AND TERMINOLOGY
“Special Units”
SI Units
Exposure
Roentgen
Coulombs / kg
Dose
rad (0.01 Gy)
Gray (100 rad)
Dose Equiv
rem (0.01 Sv)
Sievert (100 rem)
Activity
Curie (2.22 E12 dpm)
Becquerel (1dps)
1 Roentgen
= 2.58 E-4 coulomb / kg in air
= 1 esu / cm3 in air
= 87.7 ergs / gm in air
= 98 ergs / gm in soft tissue
1 rad
= 100 ergs / gm in any absorber
1 Gray
= 10,000 ergs / gm in any absorber
1 rem
= 1 rad x QF
= 0.01 Sv
H
= DQN (from ICRP 26)
H (Dose Equiv.)
= D (absorbed dose) x Q (quality factor)
x N (any other modifying factors)
Acute
Chronic
Somatic
Genetic
Teratogenic
Stochastic
Non-Stochastic
(deterministic)
72
72
UNITS AND TERMINOLOGY
“Special Units”
SI Units
Exposure
Roentgen
Coulombs / kg
Dose
rad (0.01 Gy)
Gray (100 rad)
Dose Equiv
rem (0.01 Sv)
Sievert (100 rem)
Activity
Curie (2.22 E12 dpm)
Becquerel (1dps)
1 Roentgen
= 2.58 E-4 coulomb / kg in air
= 1 esu / cm3 in air
= 87.7 ergs / gm in air
= 98 ergs / gm in soft tissue
1 rad
= 100 ergs / gm in any absorber
1 Gray
= 10,000 ergs / gm in any absorber
1 rem
= 1 rad x QF
= 0.01 Sv
H
= DQN (from ICRP 26)
H (Dose Equiv.)
= D (absorbed dose) x Q (quality factor)
x N (any other modifying factors)
Acute
Chronic
Somatic
Genetic
Teratogenic
Stochastic
Non-Stochastic
(deterministic)
DEFINITIONS
any dose in a short period of time
any dose in a long period of time
effects in the exposed individual
effects in the offspring of the exposed
individual
effects in the exposed unborn embryo/fetus
effects for which a probability exists and
increases with increasing dose
effects for which a threshold exists effects do not occur below the threshold
(examples; cataracts, erythema, epilation,
acute radiation syndrome)
72
DEFINITIONS
any dose in a short period of time
any dose in a long period of time
effects in the exposed individual
effects in the offspring of the exposed
individual
effects in the exposed unborn embryo/fetus
effects for which a probability exists and
increases with increasing dose
effects for which a threshold exists effects do not occur below the threshold
(examples; cataracts, erythema, epilation,
acute radiation syndrome)
UNITS AND TERMINOLOGY
“Special Units”
SI Units
Exposure
Roentgen
Coulombs / kg
Dose
rad (0.01 Gy)
Gray (100 rad)
Dose Equiv
rem (0.01 Sv)
Sievert (100 rem)
Activity
Curie (2.22 E12 dpm)
Becquerel (1dps)
1 Roentgen
= 2.58 E-4 coulomb / kg in air
= 1 esu / cm3 in air
= 87.7 ergs / gm in air
= 98 ergs / gm in soft tissue
1 rad
= 100 ergs / gm in any absorber
1 Gray
= 10,000 ergs / gm in any absorber
1 rem
= 1 rad x QF
= 0.01 Sv
H
= DQN (from ICRP 26)
H (Dose Equiv.)
= D (absorbed dose) x Q (quality factor)
x N (any other modifying factors)
Acute
Chronic
Somatic
Genetic
Teratogenic
Stochastic
Non-Stochastic
(deterministic)
DEFINITIONS
any dose in a short period of time
any dose in a long period of time
effects in the exposed individual
effects in the offspring of the exposed
individual
effects in the exposed unborn embryo/fetus
effects for which a probability exists and
increases with increasing dose
effects for which a threshold exists effects do not occur below the threshold
(examples; cataracts, erythema, epilation,
acute radiation syndrome)
72
RADIOLOGICAL EMERGENCY RESPONSE
RADIOLOGICAL EMERGENCY RESPONSE
Write in Your Emergency Phone Numbers
Write in Your Emergency Phone Numbers
Supervisor:
Supervisor:
Team Office:
Team Office:
Group Office:
Group Office:
Division Office:
Division Office:
Emergency Response Team:
Emergency Response Team:
Fire Department:
Fire Department:
Hospital:
Hospital:
Guidelines for Control of Emergency Exposures
Use a dose limit of: (EPA-400)
5 rem (50 mSv)
for all emergency procedures
10 rem (100 mSv)
only for protecting major property
25 rem (250 mSv)
for lifesaving or protection of large
populations
> 25 rem (250 mSv) for lifesaving or protection of large
populations only by volunteers and
where the risks have been evaluated
Guidelines for Control of Emergency Exposures
Use a dose limit of: (EPA-400)
5 rem (50 mSv)
for all emergency procedures
10 rem (100 mSv)
only for protecting major property
25 rem (250 mSv)
for lifesaving or protection of large
populations
> 25 rem (250 mSv) for lifesaving or protection of large
populations only by volunteers and
where the risks have been evaluated
73
73
RADIOLOGICAL EMERGENCY RESPONSE
RADIOLOGICAL EMERGENCY RESPONSE
Write in Your Emergency Phone Numbers
Write in Your Emergency Phone Numbers
Supervisor:
Supervisor:
Team Office:
Team Office:
Group Office:
Group Office:
Division Office:
Division Office:
Emergency Response Team:
Emergency Response Team:
Fire Department:
Fire Department:
Hospital:
Hospital:
Guidelines for Control of Emergency Exposures
Use a dose limit of: (EPA-400)
5 rem (50 mSv)
for all emergency procedures
10 rem (100 mSv)
only for protecting major property
25 rem (250 mSv)
for lifesaving or protection of large
populations
> 25 rem (250 mSv) for lifesaving or protection of large
populations only by volunteers and
where the risks have been evaluated
Guidelines for Control of Emergency Exposures
Use a dose limit of: (EPA-400)
5 rem (50 mSv)
for all emergency procedures
10 rem (100 mSv)
only for protecting major property
25 rem (250 mSv)
for lifesaving or protection of large
populations
> 25 rem (250 mSv) for lifesaving or protection of large
populations only by volunteers and
where the risks have been evaluated
73
73
EMERGENCY RESPONSE
EMERGENCY RESPONSE
SWIMS for Radiological and Other Emergencies
Only under extreme radiological conditions such as external
radiation greater than 100 rem / hr or airborne radioactivity
concentrations greater than 100,000 DAC would the radiological
emergency take precedence over serious personnel injuries.
Hazardous conditions such as atmospheres that are IDLH
would require you to implement controls to protect the
emergency responders. Therefore, you would not attempt to
move a seriously injured person before medical personnel
arrived unless the radiological or other hazardous condition
presented a greater danger to that person and yourself.
SWIMS for Radiological and Other Emergencies
Only under extreme radiological conditions such as external
radiation greater than 100 rem / hr or airborne radioactivity
concentrations greater than 100,000 DAC would the radiological
emergency take precedence over serious personnel injuries.
Hazardous conditions such as atmospheres that are IDLH
would require you to implement controls to protect the
emergency responders. Therefore, you would not attempt to
move a seriously injured person before medical personnel
arrived unless the radiological or other hazardous condition
presented a greater danger to that person and yourself.
Stop or Secure operations in the area. If applicable, secure the
operation causing the emergency.
Stop or Secure operations in the area. If applicable, secure the
operation causing the emergency.
Warn others in the area as you are evacuating. Do not search
for potentially missing personnel at this stage of the emergency.
Warn others in the area as you are evacuating. Do not search
for potentially missing personnel at this stage of the emergency.
Isolate the source of the radiation or radioactivity or other
contaminant or hazard only if you understand the operation and
are qualified to isolate the source.
Isolate the source of the radiation or radioactivity or other
contaminant or hazard only if you understand the operation and
are qualified to isolate the source.
Minimize individual exposure and contamination. Control the
entry points to the area if possible.
Minimize individual exposure and contamination. Control the
entry points to the area if possible.
Secure unfiltered ventilation. Evaluate the radiological or other
hazardous condition and advise facility personnel on ventilation
control.
74
Secure unfiltered ventilation. Evaluate the radiological or other
hazardous condition and advise facility personnel on ventilation
control.
74
EMERGENCY RESPONSE
EMERGENCY RESPONSE
SWIMS for Radiological and Other Emergencies
Only under extreme radiological conditions such as external
radiation greater than 100 rem / hr or airborne radioactivity
concentrations greater than 100,000 DAC would the radiological
emergency take precedence over serious personnel injuries.
Hazardous conditions such as atmospheres that are IDLH
would require you to implement controls to protect the
emergency responders. Therefore, you would not attempt to
move a seriously injured person before medical personnel
arrived unless the radiological or other hazardous condition
presented a greater danger to that person and yourself.
SWIMS for Radiological and Other Emergencies
Only under extreme radiological conditions such as external
radiation greater than 100 rem / hr or airborne radioactivity
concentrations greater than 100,000 DAC would the radiological
emergency take precedence over serious personnel injuries.
Hazardous conditions such as atmospheres that are IDLH
would require you to implement controls to protect the
emergency responders. Therefore, you would not attempt to
move a seriously injured person before medical personnel
arrived unless the radiological or other hazardous condition
presented a greater danger to that person and yourself.
Stop or Secure operations in the area. If applicable, secure the
operation causing the emergency.
Stop or Secure operations in the area. If applicable, secure the
operation causing the emergency.
Warn others in the area as you are evacuating. Do not search
for potentially missing personnel at this stage of the emergency.
Warn others in the area as you are evacuating. Do not search
for potentially missing personnel at this stage of the emergency.
Isolate the source of the radiation or radioactivity or other
contaminant or hazard only if you understand the operation and
are qualified to isolate the source.
Isolate the source of the radiation or radioactivity or other
contaminant or hazard only if you understand the operation and
are qualified to isolate the source.
Minimize individual exposure and contamination. Control the
entry points to the area if possible.
Minimize individual exposure and contamination. Control the
entry points to the area if possible.
Secure unfiltered ventilation. Evaluate the radiological or other
hazardous condition and advise facility personnel on ventilation
control.
74
Secure unfiltered ventilation. Evaluate the radiological or other
hazardous condition and advise facility personnel on ventilation
control.
74
HAZARD CONTROL PRIORITIES
DURING MEDICAL EMERGENCIES
HAZARD CONTROL PRIORITIES
DURING MEDICAL EMERGENCIES
Immediate treatment by trained medical personnel should be
sought for any serious injuries such as those involving profuse
bleeding or broken bones. The order of priority should be to
protect lives, protect property, and then to control the spread of
contamination.
Immediate treatment by trained medical personnel should be
sought for any serious injuries such as those involving profuse
bleeding or broken bones. The order of priority should be to
protect lives, protect property, and then to control the spread of
contamination.
Identifying a Major Injury
Identifying a Major Injury
Consider the following points in determining if the injury should
be handled as a major injury.
Any head injury (from base of neck to top of head)
Any loss of consciousness
Any disorientation
Any convulsion
Any loss of sensation
Any loss of motor function
Limbs at abnormal angles
Amputations
Any burn of the face, hands, feet, or genitals
(chemical, thermal, or radiation)
Any burn larger than the palm of your hand
Any inhalation of any abnormal substance
Profuse bleeding
Abnormal breathing patterns
Consider the following points in determining if the injury should
be handled as a major injury.
Any head injury (from base of neck to top of head)
Any loss of consciousness
Any disorientation
Any convulsion
Any loss of sensation
Any loss of motor function
Limbs at abnormal angles
Amputations
Any burn of the face, hands, feet, or genitals
(chemical, thermal, or radiation)
Any burn larger than the palm of your hand
Any inhalation of any abnormal substance
Profuse bleeding
Abnormal breathing patterns
75
75
HAZARD CONTROL PRIORITIES
DURING MEDICAL EMERGENCIES
0HAZARD CONTROL PRIORITIES
DURING MEDICAL EMERGENCIES
Immediate treatment by trained medical personnel should be
sought for any serious injuries such as those involving profuse
bleeding or broken bones. The order of priority should be to
protect lives, protect property, and then to control the spread of
contamination.
Immediate treatment by trained medical personnel should be
sought for any serious injuries such as those involving profuse
bleeding or broken bones. The order of priority should be to
protect lives, protect property, and then to control the spread of
contamination.
Identifying a Major Injury
Identifying a Major Injury
Consider the following points in determining if the injury should
be handled as a major injury.
Any head injury (from base of neck to top of head)
Any loss of consciousness
Any disorientation
Any convulsion
Any loss of sensation
Any loss of motor function
Limbs at abnormal angles
Amputations
Any burn of the face, hands, feet, or genitals
(chemical, thermal, or radiation)
Any burn larger than the palm of your hand
Any inhalation of any abnormal substance
Profuse bleeding
Abnormal breathing patterns
Consider the following points in determining if the injury should
be handled as a major injury.
Any head injury (from base of neck to top of head)
Any loss of consciousness
Any disorientation
Any convulsion
Any loss of sensation
Any loss of motor function
Limbs at abnormal angles
Amputations
Any burn of the face, hands, feet, or genitals
(chemical, thermal, or radiation)
Any burn larger than the palm of your hand
Any inhalation of any abnormal substance
Profuse bleeding
Abnormal breathing patterns
75
75
Major Injuries Occurring in Hazardous Areas
Major Injuries Occurring in Hazardous Areas
Protect yourself - consider the magnitude of any radiation field,
airborne contamination, or other hazard.
Protect yourself - consider the magnitude of any radiation field,
airborne contamination, or other hazard.
Stay with the patient unless doing so puts you at immediate risk
to life or health.
Stay with the patient unless doing so puts you at immediate risk
to life or health.
Don’t move the patient unless there is a danger from some
environmental emergency such as fire, explosion, hazardous
material spill, or radiation field.
Don’t move the patient unless there is a danger from some
environmental emergency such as fire, explosion, hazardous
material spill, or radiation field.
If you must move the patient, drag them by either the hands or
the feet to a safe area.
If you must move the patient, drag them by either the hands or
the feet to a safe area.
Apply First Aid Only if you are trained to do so.
Apply First Aid Only if you are trained to do so.
Secure help - yell or phone, but don’t leave the patient unless
necessary.
Secure help - yell or phone, but don’t leave the patient unless
necessary.
Send someone to meet the ambulance to guide the medical
personnel to the patient.
Send someone to meet the ambulance to guide the medical
personnel to the patient.
Prepare the area for access by the medical team.
Prepare the area for access by the medical team.
Begin a gross hazard evaluation of the immediate area near the
patient, beginning with the patient.
Begin a gross hazard evaluation of the immediate area near the
patient, beginning with the patient.
Be sure to survey any object that caused the injury.
Be sure to survey any object that caused the injury.
Provide information to medical personnel about the patient
(what happened, how, when, location of phone and exits,
indicate which areas on the patient are contaminated and include
contamination values).
76
Provide information to medical personnel about the patient
(what happened, how, when, location of phone and exits,
indicate which areas on the patient are contaminated and include
contamination values).
76
Major Injuries Occurring in Hazardous Areas
Major Injuries Occurring in Hazardous Areas
Protect yourself - consider the magnitude of any radiation field,
airborne contamination, or other hazard.
Protect yourself - consider the magnitude of any radiation field,
airborne contamination, or other hazard.
Stay with the patient unless doing so puts you at immediate risk
to life or health.
Stay with the patient unless doing so puts you at immediate risk
to life or health.
Don’t move the patient unless there is a danger from some
environmental emergency such as fire, explosion, hazardous
material spill, or radiation field.
Don’t move the patient unless there is a danger from some
environmental emergency such as fire, explosion, hazardous
material spill, or radiation field.
If you must move the patient, drag them by either the hands or
the feet to a safe area.
If you must move the patient, drag them by either the hands or
the feet to a safe area.
Apply First Aid Only if you are trained to do so.
Apply First Aid Only if you are trained to do so.
Secure help - yell or phone, but don’t leave the patient unless
necessary.
Secure help - yell or phone, but don’t leave the patient unless
necessary.
Send someone to meet the ambulance to guide the medical
personnel to the patient.
Send someone to meet the ambulance to guide the medical
personnel to the patient.
Prepare the area for access by the medical team.
Prepare the area for access by the medical team.
Begin a gross hazard evaluation of the immediate area near the
patient, beginning with the patient.
Begin a gross hazard evaluation of the immediate area near the
patient, beginning with the patient.
Be sure to survey any object that caused the injury.
Be sure to survey any object that caused the injury.
Provide information to medical personnel about the patient
(what happened, how, when, location of phone and exits,
indicate which areas on the patient are contaminated and include
contamination values).
76
Provide information to medical personnel about the patient
(what happened, how, when, location of phone and exits,
indicate which areas on the patient are contaminated and include
contamination values).
76
CONTAMINATED / INJURED PERSON FORM
Indicate on this form any injuries or contamination and the
extent of the injury or contamination.
77
CONTAMINATED / INJURED PERSON FORM
Indicate on this form any injuries or contamination and the
extent of the injury or contamination.
77
CONTAMINATED / INJURED PERSON FORM
Indicate on this form any injuries or contamination and the
extent of the injury or contamination.
77
CONTAMINATED / INJURED PERSON FORM
Indicate on this form any injuries or contamination and the
extent of the injury or contamination.
77
PUBLIC RADIATION DOSES
Average per capita US Dose
200 mrem (2 mSv) / yr
Living in Los Alamos (7000' elev) 327 mrem (3.27 mSv)/yr
Flying from NY to LA
2.5 mrem (25 ìSv) / trip
Chest x-ray
10 mrem (0.1mSv)/exam
Full mouth dental x-ray
9 mrem (90 ìSv) / exam
The external dose rate for cosmic rays doubles for each mile
increase in elevation.
PUBLIC RADIATION DOSES
Average per capita US Dose
200 mrem (2 mSv) / yr
Living in Los Alamos (7000' elev) 327 mrem (3.27 mSv)/yr
Flying from NY to LA
2.5 mrem (25 ìSv) / trip
Chest x-ray
10 mrem (0.1mSv)/exam
Full mouth dental x-ray
9 mrem (90 ìSv) / exam
The external dose rate for cosmic rays doubles for each mile
increase in elevation.
BACKGROUND RADIATION
Cosmic
= 28 mrem (0.28 mSv) / yr
Rocks
= 28 mrem (0.28 mSv) / yr
Internal
= 36 mrem (0.36 mSv) / yr
Medical x-rays
= 20 to 30 mrem (0.2 to 0.3 mSv)/yr
Nuclear medicine
= 2 mrem / yr
TOTAL US Ave
. 120 mrem / yr
US Ave HE from radon
= 200 mrem / yr
Ave HE from medical x-ray procedures:
Skull 20 mrem (0.2 mSv)
Upper GI 245 mrem (2.45 mSv)
Hip 65 mrem (0.65 mSv)
Chest 6 mrem (60 ìSv),
Kidney 55 mrem (0.55 mSv)
Dental 55 mrem (0.55 mSv)
BACKGROUND RADIATION
Cosmic
= 28 mrem (0.28 mSv) / yr
Rocks
= 28 mrem (0.28 mSv) / yr
Internal
= 36 mrem (0.36 mSv) / yr
Medical x-rays
= 20 to 30 mrem (0.2 to 0.3 mSv)/yr
Nuclear medicine
= 2 mrem / yr
TOTAL US Ave
. 120 mrem / yr
US Ave HE from radon
= 200 mrem / yr
Ave HE from medical x-ray procedures:
Skull 20 mrem (0.2 mSv)
Upper GI 245 mrem (2.45 mSv)
Hip 65 mrem (0.65 mSv)
Chest 6 mrem (60 ìSv),
Kidney 55 mrem (0.55 mSv)
Dental 55 mrem (0.55 mSv)
Occupational Doses
airline flight crew
nuclear power plant
Grand Central Station workers
medical personnel
DOE employees
Occupational Doses
airline flight crew
nuclear power plant
Grand Central Station workers
medical personnel
DOE employees
mrem /yr
1,000
700
120
70
44
mSv/yr
10
7
1.2
0.7
0.44
78
mrem /yr
1,000
700
120
70
44
mSv/yr
10
7
1.2
0.7
0.44
78
PUBLIC RADIATION DOSES
Average per capita US Dose
200 mrem (2 mSv) / yr
Living in Los Alamos (7000' elev) 327 mrem (3.27 mSv)/yr
Flying from NY to LA
2.5 mrem (25 ìSv) / trip
Chest x-ray
10 mrem (0.1mSv)/exam
Full mouth dental x-ray
9 mrem (90 ìSv) / exam
The external dose rate for cosmic rays doubles for each mile
increase in elevation.
PUBLIC RADIATION DOSES
Average per capita US Dose
200 mrem (2 mSv) / yr
Living in Los Alamos (7000' elev) 327 mrem (3.27 mSv)/yr
Flying from NY to LA
2.5 mrem (25 ìSv) / trip
Chest x-ray
10 mrem (0.1mSv)/exam
Full mouth dental x-ray
9 mrem (90 ìSv) / exam
The external dose rate for cosmic rays doubles for each mile
increase in elevation.
BACKGROUND RADIATION
Cosmic
= 28 mrem (0.28 mSv) / yr
Rocks
= 28 mrem (0.28 mSv) / yr
Internal
= 36 mrem (0.36 mSv) / yr
Medical x-rays
= 20 to 30 mrem (0.2 to 0.3 mSv)/yr
Nuclear medicine
= 2 mrem / yr
TOTAL US Ave
. 120 mrem / yr
US Ave HE from radon
= 200 mrem / yr
Ave HE from medical x-ray procedures:
Skull 20 mrem (0.2 mSv)
Upper GI 245 mrem (2.45 mSv)
Hip 65 mrem (0.65 mSv)
Chest 6 mrem (60 ìSv),
Kidney 55 mrem (0.55 mSv)
Dental 55 mrem (0.55 mSv)
BACKGROUND RADIATION
Cosmic
= 28 mrem (0.28 mSv) / yr
Rocks
= 28 mrem (0.28 mSv) / yr
Internal
= 36 mrem (0.36 mSv) / yr
Medical x-rays
= 20 to 30 mrem (0.2 to 0.3 mSv)/yr
Nuclear medicine
= 2 mrem / yr
TOTAL US Ave
. 120 mrem / yr
US Ave HE from radon
= 200 mrem / yr
Ave HE from medical x-ray procedures:
Skull 20 mrem (0.2 mSv)
Upper GI 245 mrem (2.45 mSv)
Hip 65 mrem (0.65 mSv)
Chest 6 mrem (60 ìSv),
Kidney 55 mrem (0.55 mSv)
Dental 55 mrem (0.55 mSv)
Occupational Doses
airline flight crew
nuclear power plant
Grand Central Station workers
medical personnel
DOE employees
Occupational Doses
airline flight crew
nuclear power plant
Grand Central Station workers
medical personnel
DOE employees
78
mrem /yr
1,000
700
120
70
44
mSv/yr
10
7
1.2
0.7
0.44
78
mrem /yr
1,000
700
120
70
44
mSv/yr
10
7
1.2
0.7
0.44
RADON FACTS
222
=
3 DAC Rn (including progeny)
=
1.3E5 MeV / liter of air á energy
=
100 pCi / liter (1E-7 uCi / mL)
3
=
20.8 uJoules / M
1 working level-month = 1 pCi / L in air thru evaporation
1 working level
RADON FACTS
222
=
3 DAC Rn (including progeny)
=
1.3E5 MeV / liter of air á energy
=
100 pCi / liter (1E-7 uCi / mL)
3
=
20.8 uJoules / M
1 working level-month = 1 pCi / L in air thru evaporation
1 working level
EPA ACTION LEVELS FOR RADON GAS IN HOMES
Concentration (pCi / L)Sampling Frequency
0 - 4initial and no follow up
EPA Recommends Mitigation at > 4 pCi / L
4 -20one year and follow up
20 -2003 months and follow up
> 200
Implement radon reduction methods
4 pCi / L in living area = 1.03 working level-month = 1 rem
EPA ACTION LEVELS FOR RADON GAS IN HOMES
Concentration (pCi / L)Sampling Frequency
0 - 4initial and no follow up
EPA Recommends Mitigation at > 4 pCi / L
4 -20one year and follow up
20 -2003 months and follow up
> 200
Implement radon reduction methods
4 pCi / L in living area = 1.03 working level-month = 1 rem
PROPOSED EPA ACTION LEVELS
FOR RADON IN DRINKING WATER
Maximum Contaminant Level (MCL) is 300 pCi / L of radon in
water of community water systems (CWS).
Alternative Maximum Contaminant Level (AMCL) is 4,000 pCi
/ L of radon in water of community water systems.
PROPOSED EPA ACTION LEVELS
FOR RADON IN DRINKING WATER
Maximum Contaminant Level (MCL) is 300 pCi / L of radon in
water of community water systems (CWS).
Alternative Maximum Contaminant Level (AMCL) is 4,000 pCi
/ L of radon in water of community water systems.
To comply with the AMCL limit the state or the CWS
(Community Water System) must implement a Multi-Media
Mitigation plan to address the radon in the air of residences.
The proposed rule would not apply to CWSs that use solely
surface water.
To comply with the AMCL limit the state or the CWS
(Community Water System) must implement a Multi-Media
Mitigation plan to address the radon in the air of residences.
The proposed rule would not apply to CWSs that use solely
surface water.
The proposed rule requires monitoring for radon in drinking
water. The monitoring frequency varies from once per quarter
to once in 9 years based on radon concentrations.
The proposed rule requires monitoring for radon in drinking
water. The monitoring frequency varies from once per quarter
to once in 9 years based on radon concentrations.
RADON FACTS
222
=
3 DAC Rn (including progeny)
=
1.3E5 MeV / liter of air á energy
=
100 pCi / liter (1E-7 uCi / mL)
3
=
20.8 uJoules / M
1 working level-month = 1 pCi / L in air thru evaporation
1 working level
RADON FACTS
222
=
3 DAC Rn (including progeny)
=
1.3E5 MeV / liter of air á energy
=
100 pCi / liter (1E-7 uCi / mL)
3
=
20.8 uJoules / M
1 working level-month = 1 pCi / L in air thru evaporation
1 working level
EPA ACTION LEVELS FOR RADON GAS IN HOMES
Concentration (pCi / L)Sampling Frequency
0 - 4initial and no follow up
EPA Recommends Mitigation at > 4 pCi / L
4 -20one year and follow up
20 -2003 months and follow up
> 200
Implement radon reduction methods
4 pCi / L in living area = 1.03 working level-month = 1 rem
EPA ACTION LEVELS FOR RADON GAS IN HOMES
Concentration (pCi / L)Sampling Frequency
0 - 4initial and no follow up
EPA Recommends Mitigation at > 4 pCi / L
4 -20one year and follow up
20 -2003 months and follow up
> 200
Implement radon reduction methods
4 pCi / L in living area = 1.03 working level-month = 1 rem
PROPOSED EPA ACTION LEVELS
FOR RADON IN DRINKING WATER
Maximum Contaminant Level (MCL) is 300 pCi / L of radon in
water of community water systems (CWS).
Alternative Maximum Contaminant Level (AMCL) is 4,000 pCi
/ L of radon in water of community water systems.
PROPOSED EPA ACTION LEVELS
FOR RADON IN DRINKING WATER
Maximum Contaminant Level (MCL) is 300 pCi / L of radon in
water of community water systems (CWS).
Alternative Maximum Contaminant Level (AMCL) is 4,000 pCi
/ L of radon in water of community water systems.
To comply with the AMCL limit the state or the CWS
(Community Water System) must implement a Multi-Media
Mitigation plan to address the radon in the air of residences.
The proposed rule would not apply to CWSs that use solely
surface water.
To comply with the AMCL limit the state or the CWS
(Community Water System) must implement a Multi-Media
Mitigation plan to address the radon in the air of residences.
The proposed rule would not apply to CWSs that use solely
surface water.
The proposed rule requires monitoring for radon in drinking
water. The monitoring frequency varies from once per quarter
to once in 9 years based on radon concentrations.
The proposed rule requires monitoring for radon in drinking
water. The monitoring frequency varies from once per quarter
to once in 9 years based on radon concentrations.
COMPARATIVE RISKS OF RADIATION EXPOSURE
Smoking 1 pack of cigarettes / day
20% overweight
Average US alcohol consumption
Home accidents
Estimated Days
of Life Lost
2,370
985
130
95
OCCUPATIONAL RISKS
Estimated Days
Occupation
of Life Lost
demolition
1,500
mining
1,100
firefighting
800
railroad
500
farming
300
construction
200
transportation & public utilities
160
average of all occupations
60
government
55
radiation dose of 1 rem (10 mSv) per year
50
service
45
trade
30
single radiation dose of 1 rem (10 mSv)
1.5
COMPARATIVE RISKS OF RADIATION EXPOSURE
Estimated Days
of Life Lost
2,370
985
130
95
OCCUPATIONAL RISKS
Estimated Days
Occupation
of Life Lost
demolition
1,500
mining
1,100
firefighting
800
railroad
500
farming
300
construction
200
transportation & public utilities
160
average of all occupations
60
government
55
radiation dose of 1 rem (10 mSv) per year
50
service
45
trade
30
single radiation dose of 1 rem (10 mSv)
1.5
80
Smoking 1 pack of cigarettes / day
20% overweight
Average US alcohol consumption
Home accidents
Estimated Days
of Life Lost
2,370
985
130
95
OCCUPATIONAL RISKS
Estimated Days
Occupation
of Life Lost
demolition
1,500
mining
1,100
firefighting
800
railroad
500
farming
300
construction
200
transportation & public utilities
160
average of all occupations
60
government
55
radiation dose of 1 rem (10 mSv) per year
50
service
45
trade
30
single radiation dose of 1 rem (10 mSv)
1.5
80
80
Smoking 1 pack of cigarettes / day
20% overweight
Average US alcohol consumption
Home accidents
COMPARATIVE RISKS OF RADIATION EXPOSURE
COMPARATIVE RISKS OF RADIATION EXPOSURE
Smoking 1 pack of cigarettes / day
20% overweight
Average US alcohol consumption
Home accidents
Estimated Days
of Life Lost
2,370
985
130
95
OCCUPATIONAL RISKS
Estimated Days
Occupation
of Life Lost
demolition
1,500
mining
1,100
firefighting
800
railroad
500
farming
300
construction
200
transportation & public utilities
160
average of all occupations
60
government
55
radiation dose of 1 rem (10 mSv) per year
50
service
45
trade
30
single radiation dose of 1 rem (10 mSv)
1.5
80
Relative Risk
Relative Risk
Your overall risk of dying is 1 in 1
Heart disease
Cancer
Stroke
Motor vehicle accident
Suicide
Falling
Firearm assault
Pedestrian accident
Drowning
Motorcycle accident
Fire or smoke
Bicycle accident
Air / space accident
Accidental firearm discharge
Accidental electrocution
Alcohol poisoning
Hot weather
Hornet, wasp, or bee sting
Legal execution
Lightning
Earthquake
Flood
Fireworks discharge
1 in 5
1 in 7
1 in 24
1 in 84
1 in 119
1 in 218
1 in 314
1 in 626
1 in 1,008
1 in 1,020
1 in 1,113
1 in 4,919
1 in 5,051
1 in 5,134
1 in 9,968
1 in 10,048
1 in 13,729
1 in 56,789
1 in 62,468
1 in 79,746
1 in 117,127
1 in 144,156
1 in 340,733
1 in 5
1 in 7
1 in 24
1 in 84
1 in 119
1 in 218
1 in 314
1 in 626
1 in 1,008
1 in 1,020
1 in 1,113
1 in 4,919
1 in 5,051
1 in 5,134
1 in 9,968
1 in 10,048
1 in 13,729
1 in 56,789
1 in 62,468
1 in 79,746
1 in 117,127
1 in 144,156
1 in 340,733
Relative Risk
Relative Risk
Your overall risk of dying is 1 in 1
81
Heart disease
Cancer
Stroke
Motor vehicle accident
Suicide
Falling
Firearm assault
Pedestrian accident
Drowning
Motorcycle accident
Fire or smoke
Bicycle accident
Air / space accident
Accidental firearm discharge
Accidental electrocution
Alcohol poisoning
Hot weather
Hornet, wasp, or bee sting
Legal execution
Lightning
Earthquake
Flood
Fireworks discharge
81
81
Heart disease
Cancer
Stroke
Motor vehicle accident
Suicide
Falling
Firearm assault
Pedestrian accident
Drowning
Motorcycle accident
Fire or smoke
Bicycle accident
Air / space accident
Accidental firearm discharge
Accidental electrocution
Alcohol poisoning
Hot weather
Hornet, wasp, or bee sting
Legal execution
Lightning
Earthquake
Flood
Fireworks discharge
Your overall risk of dying is 1 in 1
1 in 5
1 in 7
1 in 24
1 in 84
1 in 119
1 in 218
1 in 314
1 in 626
1 in 1,008
1 in 1,020
1 in 1,113
1 in 4,919
1 in 5,051
1 in 5,134
1 in 9,968
1 in 10,048
1 in 13,729
1 in 56,789
1 in 62,468
1 in 79,746
1 in 117,127
1 in 144,156
1 in 340,733
Your overall risk of dying is 1 in 1
Heart disease
Cancer
Stroke
Motor vehicle accident
Suicide
Falling
Firearm assault
Pedestrian accident
Drowning
Motorcycle accident
Fire or smoke
Bicycle accident
Air / space accident
Accidental firearm discharge
Accidental electrocution
Alcohol poisoning
Hot weather
Hornet, wasp, or bee sting
Legal execution
Lightning
Earthquake
Flood
Fireworks discharge
81
1 in 5
1 in 7
1 in 24
1 in 84
1 in 119
1 in 218
1 in 314
1 in 626
1 in 1,008
1 in 1,020
1 in 1,113
1 in 4,919
1 in 5,051
1 in 5,134
1 in 9,968
1 in 10,048
1 in 13,729
1 in 56,789
1 in 62,468
1 in 79,746
1 in 117,127
1 in 144,156
1 in 340,733
Government Agency Websites
Government Agency Websites
www.cdc.gov
www.cirm s.tis.doe.gov
www.defenselink.m il
www.dnfsb.gov
www.dot.gov
www.edf.fr
www.eh.doe.gov/nepa
www.energy.gov
www.epa.gov/radiation
www.fda.gov/cdrh
www.fedworld.gov
www.fem a.gov
www.lanl.gov
www.lbl.gov
www.lib.lsu.edu/gov/alpha
www.llnl.gov
www.nrc.gov
www.doe.gov
www.nrc.gov/about-nrc/regulatory/research/radiologicaltoolbox.htm l
www.ornl.gov
www.osha.gov
www.srs.gov
www.cdc.gov
www.cirm s.tis.doe.gov
www.defenselink.m il
www.dnfsb.gov
www.dot.gov
www.edf.fr
www.eh.doe.gov/nepa
www.energy.gov
www.epa.gov/radiation
www.fda.gov/cdrh
www.fedworld.gov
www.fem a.gov
www.lanl.gov
www.lbl.gov
www.lib.lsu.edu/gov/alpha
www.llnl.gov
www.nrc.gov
www.doe.gov
www.nrc.gov/about-nrc/regulatory/research/radiologicaltoolbox.htm l
www.ornl.gov
www.osha.gov
www.srs.gov
82
82
Government Agency Websites
Government Agency Websites
www.cdc.gov
www.cirm s.tis.doe.gov
www.defenselink.m il
www.dnfsb.gov
www.dot.gov
www.edf.fr
www.eh.doe.gov/nepa
www.energy.gov
www.epa.gov/radiation
www.fda.gov/cdrh
www.fedworld.gov
www.fem a.gov
www.lanl.gov
www.lbl.gov
www.lib.lsu.edu/gov/alpha
www.llnl.gov
www.nrc.gov
www.doe.gov
www.nrc.gov/about-nrc/regulatory/research/radiologicaltoolbox.htm l
www.ornl.gov
www.osha.gov
www.srs.gov
www.cdc.gov
www.cirm s.tis.doe.gov
www.defenselink.m il
www.dnfsb.gov
www.dot.gov
www.edf.fr
www.eh.doe.gov/nepa
www.energy.gov
www.epa.gov/radiation
www.fda.gov/cdrh
www.fedworld.gov
www.fem a.gov
www.lanl.gov
www.lbl.gov
www.lib.lsu.edu/gov/alpha
www.llnl.gov
www.nrc.gov
www.doe.gov
www.nrc.gov/about-nrc/regulatory/research/radiologicaltoolbox.htm l
www.ornl.gov
www.osha.gov
www.srs.gov
82
82
Professional Organizations Websites
Professional Organizations Websites
www.aarst.org
www.abm pexam .com
www.acgih.org/hom e.htm
www.aiha.org
www.am ug.us
www.ans.org
www.ansi.org
www.cea.fr
www.edf.fr
www.hps.org
www.hps.org/iarpe
www.hps1.org/aahp
www.icrp.org
www.iaea.org/worldatom
www.hps1.org/aahp/abhp/abhp.htm
www.i-i-s.net
www.irpa.net
www.ncrp.com
www.ncrponline.org
www.nea.fr
www.nrrpt.org
www.nrsb.org
www.nrsi.org
www.nuclearsafety.gc.ca
www.radres.org
www.rsna.org
www.sra.org
www.aarst.org
www.abm pexam .com
www.acgih.org/hom e.htm
www.aiha.org
www.am ug.us
www.ans.org
www.ansi.org
www.cea.fr
www.edf.fr
www.hps.org
www.hps.org/iarpe
www.hps1.org/aahp
www.icrp.org
www.iaea.org/worldatom
www.hps1.org/aahp/abhp/abhp.htm
www.i-i-s.net
www.irpa.net
www.ncrp.com
www.ncrponline.org
www.nea.fr
www.nrrpt.org
www.nrsb.org
www.nrsi.org
www.nuclearsafety.gc.ca
www.radres.org
www.rsna.org
www.sra.org
83
83
Professional Organizations Websites
Professional Organizations Websites
www.aarst.org
www.abm pexam .com
www.acgih.org/hom e.htm
www.aiha.org
www.am ug.us
www.ans.org
www.ansi.org
www.cea.fr
www.edf.fr
www.hps.org
www.hps.org/iarpe
www.hps1.org/aahp
www.icrp.org
www.iaea.org/worldatom
www.hps1.org/aahp/abhp/abhp.htm
www.i-i-s.net
www.irpa.net
www.ncrp.com
www.ncrponline.org
www.nea.fr
www.nrrpt.org
www.nrsb.org
www.nrsi.org
www.nuclearsafety.gc.ca
www.radres.org
www.rsna.org
www.sra.org
www.aarst.org
www.abm pexam .com
www.acgih.org/hom e.htm
www.aiha.org
www.am ug.us
www.ans.org
www.ansi.org
www.cea.fr
www.edf.fr
www.hps.org
www.hps.org/iarpe
www.hps1.org/aahp
www.icrp.org
www.iaea.org/worldatom
www.hps1.org/aahp/abhp/abhp.htm
www.i-i-s.net
www.irpa.net
www.ncrp.com
www.ncrponline.org
www.nea.fr
www.nrrpt.org
www.nrsb.org
www.nrsi.org
www.nuclearsafety.gc.ca
www.radres.org
www.rsna.org
www.sra.org
83
83
ANNEX
Tc-99m Heart Stress Test
ANNEX
Tc-99m Heart Stress Test
Patient is 69 year old overweight male, being treated for high
blood pressure, high cholesterol, and type II diabetes.
Patient is 69 year old overweight male, being treated for high
blood pressure, high cholesterol, and type II diabetes.
09:07
Injected with 5 mCi Tc-99m Cardiolite
Effective dose is ~ 6.7 mSv (670 mRem)
Tc-99m 141 kev gamma radiation
6.0058 hour half-life
09:07
Injected with 5 mCi Tc-99m Cardiolite
Effective dose is ~ 6.7 mSv (670 mRem)
Tc-99m 141 kev gamma radiation
6.0058 hour half-life
09:12
20 mR/hr contact at injection point
3.15 mR/hr at 30 cm
09:12
20 mR/hr contact at injection point
3.15 mR/hr at 30 cm
09:19
8.15 mR/hr contact at heart
09:19
8.15 mR/hr contact at heart
09:26
16 mR/hr contact at injection point
7.7 mR/hr contact at heart
3 mR/hr contact at extremities
1.8 mR/hr at 30 cm
09:26
16 mR/hr contact at injection point
7.7 mR/hr contact at heart
3 mR/hr contact at extremities
1.8 mR/hr at 30 cm
10:08
10.8 mR/hr contact at injection point
7.5 mR/hr contact at heart
3.2 mR/hr contact right arm (opposite injection)
1.6 mR/hr at 30 cm
10:08
10.8 mR/hr contact at injection point
7.5 mR/hr contact at heart
3.2 mR/hr contact right arm (opposite injection)
1.6 mR/hr at 30 cm
11:06
17.2 mR/hr contact at injection point
6.13 mR/hr contact at heart
3.7 mR/hr contact right arm (opposite injection)
1.4 mR/hr at 30 cm
11:06
17.2 mR/hr contact at injection point
6.13 mR/hr contact at heart
3.7 mR/hr contact right arm (opposite injection)
1.4 mR/hr at 30 cm
ANNEX
Tc-99m Heart Stress Test
ANNEX
Tc-99m Heart Stress Test
Patient is 69 year old overweight male, being treated for high
blood pressure, high cholesterol, and type II diabetes.
Patient is 69 year old overweight male, being treated for high
blood pressure, high cholesterol, and type II diabetes.
09:07
Injected with 5 mCi Tc-99m Cardiolite
Effective dose is ~ 6.7 mSv (670 mRem)
Tc-99m 141 kev gamma radiation
6.0058 hour half-life
09:07
Injected with 5 mCi Tc-99m Cardiolite
Effective dose is ~ 6.7 mSv (670 mRem)
Tc-99m 141 kev gamma radiation
6.0058 hour half-life
09:12
20 mR/hr contact at injection point
3.15 mR/hr at 30 cm
09:12
20 mR/hr contact at injection point
3.15 mR/hr at 30 cm
09:19
8.15 mR/hr contact at heart
09:19
8.15 mR/hr contact at heart
09:26
16 mR/hr contact at injection point
7.7 mR/hr contact at heart
3 mR/hr contact at extremities
1.8 mR/hr at 30 cm
09:26
16 mR/hr contact at injection point
7.7 mR/hr contact at heart
3 mR/hr contact at extremities
1.8 mR/hr at 30 cm
10:08
10.8 mR/hr contact at injection point
7.5 mR/hr contact at heart
3.2 mR/hr contact right arm (opposite injection)
1.6 mR/hr at 30 cm
10:08
10.8 mR/hr contact at injection point
7.5 mR/hr contact at heart
3.2 mR/hr contact right arm (opposite injection)
1.6 mR/hr at 30 cm
11:06
17.2 mR/hr contact at injection point
6.13 mR/hr contact at heart
3.7 mR/hr contact right arm (opposite injection)
1.4 mR/hr at 30 cm
11:06
17.2 mR/hr contact at injection point
6.13 mR/hr contact at heart
3.7 mR/hr contact right arm (opposite injection)
1.4 mR/hr at 30 cm
ANNEX
Tc-99m Heart Stress Test
ANNEX
Tc-99m Heart Stress Test
11:45
Injected with additional 5 mCi Tc-99m
11:45
Injected with additional 5 mCi Tc-99m
12:04
9.7 mR/hr contact at injection point
24.4 mR/hr contact at heart
2.5 mR/hr at 30 cm
12:04
9.7 mR/hr contact at injection point
24.4 mR/hr contact at heart
2.5 mR/hr at 30 cm
14:45
8.0 mR/hr contact at injection point
13.1 mR/hr contact at heart
2.6 mR/hr at 30 cm
14:45
8.0 mR/hr contact at injection point
13.1 mR/hr contact at heart
2.6 mR/hr at 30 cm
Second Day
Second Day
07:30
1.2 mR/hr contact on torso
0.6 mR/hr contact on extremities
0.24 mR/hr at 30 cm
07:30
1.2 mR/hr contact on torso
0.6 mR/hr contact on extremities
0.24 mR/hr at 30 cm
13:00
0.8 mR/hr contact on torso
0.1 mR/hr at 30 cm
13:00
0.8 mR/hr contact on torso
0.1 mR/hr at 30 cm
Patient is a radiation worker with a career in nuclear power
plants and DOE facilities. Lifetime occupational radiation
exposure is 20 mSv (2.0 Rem).
Patient is a radiation worker with a career in nuclear power
plants and DOE facilities. Lifetime occupational radiation
exposure is 20 mSv (2.0 Rem).
Patient’s family members could be exposed to radiation
due to this test. Maximum family member exposure might
be in the range of 0.2 mSv (20 mRem).
Patient’s family members could be exposed to radiation
due to this test. Maximum family member exposure might
be in the range of 0.2 mSv (20 mRem).
This medical test indicated no additional patient difficulties.
This medical test indicated no additional patient difficulties.
ANNEX
Tc-99m Heart Stress Test
ANNEX
Tc-99m Heart Stress Test
11:45
Injected with additional 5 mCi Tc-99m
11:45
Injected with additional 5 mCi Tc-99m
12:04
9.7 mR/hr contact at injection point
24.4 mR/hr contact at heart
2.5 mR/hr at 30 cm
12:04
9.7 mR/hr contact at injection point
24.4 mR/hr contact at heart
2.5 mR/hr at 30 cm
14:45
8.0 mR/hr contact at injection point
13.1 mR/hr contact at heart
2.6 mR/hr at 30 cm
14:45
8.0 mR/hr contact at injection point
13.1 mR/hr contact at heart
2.6 mR/hr at 30 cm
Second Day
Second Day
07:30
1.2 mR/hr contact on torso
0.6 mR/hr contact on extremities
0.24 mR/hr at 30 cm
07:30
1.2 mR/hr contact on torso
0.6 mR/hr contact on extremities
0.24 mR/hr at 30 cm
13:00
0.8 mR/hr contact on torso
0.1 mR/hr at 30 cm
13:00
0.8 mR/hr contact on torso
0.1 mR/hr at 30 cm
Patient is a radiation worker with a career in nuclear power
plants and DOE facilities. Lifetime occupational radiation
exposure is 20 mSv (2.0 Rem).
Patient is a radiation worker with a career in nuclear power
plants and DOE facilities. Lifetime occupational radiation
exposure is 20 mSv (2.0 Rem).
Patient’s family members could be exposed to radiation
due to this test. Maximum family member exposure might
be in the range of 0.2 mSv (20 mRem).
Patient’s family members could be exposed to radiation
due to this test. Maximum family member exposure might
be in the range of 0.2 mSv (20 mRem).
This medical test indicated no additional patient difficulties.
This medical test indicated no additional patient difficulties.