RADIATION LABORATORY REFERENCE MANUAL
University of Waterloo
Safety Office
http://www.rstp.uwaterloo.ca/
Updated June 2010
Table of Contents
Radiation Safety Program
Administration of Radiation Safety Program ...................................................................... 3
Internal Permits ................................................................................................................. 4
Non-Compliance................................................................................................................ 4
Laboratory Classification ................................................................................................... 5
Laboratory Signage ........................................................................................................... 6
Radiation Exposure
Dosimetry .......................................................................................................................... 6
Exemption Quantities......................................................................................................... 9
Conversion Table .............................................................................................................. 10
Radiation Protection
Contamination Survey Procedures .................................................................................... 11
Direct Measurement of Contamination .............................................................................. 12
Indirect Measurement of Contamination ............................................................................ 13
Instrument Selection .......................................................................................................... 14
Contamination Monitoring Records ................................................................................... 15
Regulatory Limits of Contamination................................................................................... 16
Classification of Radionuclides .......................................................................................... 17
Decontamination Protocols................................................................................................ 18
Ordering Radioisotopes ..................................................................................................... 19
Inventory............................................................................................................................ 20
Waste Disposal.................................................................................................................. 21
Laboratory Procedures ...................................................................................................... 22
Emergency Procedures
Emergency Contacts ......................................................................................................... 23
Spills Procedures............................................................................................................... 24
Contaminated Personnel ................................................................................................... 25
Air Release ........................................................................................................................ 25
Radiation Data Sheets
Isotopes ............................................................................................................................. 26
Forms
Contamination Monitoring.................................................................................................. 36
Inventory............................................................................................................................ 37
2
Administration of Radiation Safety Program
Acts and Regulations
The Government of Canada controls the uses and possession of nuclear substances using the
following legislative tools:
1. The Nuclear Safety and Control Act which created the Canadian Nuclear Safety
Commission (CNSC). The CNSC has the authority to create and enforces radiation
regulations based on the latest scientific information.
2. Regulations created under the Nuclear Safety and Control Act, which describe
operation responsibilities of the various persons involved in the use and handling of
radioisotopes.
3. Licence Conditions which are set by the CNSC and outline operational requirements
specific to the type of activity. UW's conditions are for University research.
Radiation Safety Committee
The Radiation Safety Committee's (RSC) overall responsibility is to monitor all aspects of
radionuclide use on campus. The RSC is advisory to the Provost.
Radiation Safety Officer
The Radiation Safety Officer shall administer the consolidated use license issued to the
institution by the C.N.S.C. by overseeing and coordinating all aspects of radiation safety within
the institution.
Permit Holders
Permit Holders are responsible for the day to day supervision of the workers. All permits are
approved by the RSC and issued by the RSO.
Duties and Responsibilities of Permit Holders
1. The permit holder shall insure workers and students working under their supervision:
2. receive radioisotope training and are authorized to work with radioisotopes,
3. follow the rules and regulations set out by C.N.S.C. and the University of Waterloo
Radiation Safety Committee,
4. report incidents of loss or theft to the Radiation Safety Officer ( Ext. 6268)
5. be provided with adequate facilities, equipment and supervision to ensure that workers
or students follow the rules and regulations set out by C.N.S.C. and the University of
Waterloo Radiation Safety Committee;
6. maintain inventories of all radioactive materials as well as storage and disposal records
for inspection by the Radiation Safety Officer,
7. maintain area monitoring and/or wipe test records for inspection by the Radiation Safety
Officer,
8. and wear the appropriate radiation dosimetry and participate in prescribed bioassay
programs.
3
Internal Permits
University of Waterloo researchers who wish to use radioisotopes in their work must apply for
a UW Radioisotope Permit. Information about the research project, permit holder
qualifications, laboratory facilities, type of radioisotopes used and equipment used to monitor
contamination are collected on a Permit Application Form.
The Permit Application Form is forwarded to the Radiation Safety Officer (RSO), the RSO
inspects the laboratory completing a Design Compliance form, the application and Design
Compliance Form are sent to the members of the Radiation Safety Committee for comment.
Pending approval by the Radiation Safety Committee a UW Radioisotope Permit is issued by
the Radiation Safety Officer. Internal permits are issued for a period not to exceed 2 years.
Non-Compliance
The Nuclear Safety Control Act and Regulations, Nuclear Substance and Radiation Devices
licence conditions and operating procedures outlined in this manual have been developed to
ensure the health and safety of workers/students at UW. Non-compliance with these standard
and statutes place the worker/student in contravention of federal law and UW's Policy 34 Health, Safety and Environment.
To insure compliance, the Radiation Safety Officer will inspect all laboratories using
radioisotope al least 4 times per year.
Infractions will be dealt with as follows:
1. The Radiation Safety Officer (RSO) may stop unsafe work at any time
2. First infraction by a worker will result in notification by the RSO of the infraction to the
Permit Holder and a verbal warning to the worker/student.
3. A repetition of the infraction, the RSO notifies the Permit Holder and worker of to the
consequences of a second repetition of the infraction and instructs the worker to
undergo retraining prior to resuming work with radioisotopes.
4. A second repetition of the infraction, the Radiation Safety Officer will ask the Permit
Holder to prohibit the worker/student from working with radioisotopes for a period of
time to be determined by the Radiation Safety Committee or alternatively the Permit
Holder and all workers/students working with radioisotopes may under go retraining.
5. Refusal of the Permit Holder to enforce these penalties will result in removal of the
Radioisotope Permit by the Radiation Safety Committee.
4
Laboratory Classification
A laboratory in which more than one "Exempt Quantity" of a nuclear substance is used will be
designated a Basic, Intermediate or High Level.
Laboratory Designation
1. Non Regulated if the total quantity of radioisotopes stored or used does not exceed the
Exempt Quantity Limit for the radioisotope
2. Basic Level laboratory if the largest quantity of radioisotopes stored or used does not
exceed 5 ALI.
3. Intermediate Level laboratory if the largest quantity of radioisotopes stored or used does
not exceed 50 ALI.
4. High Level laboratory if the largest quantity of radioisotopes stored or used does not
exceed 500 ALI
Maximum Quantities of radioisotopes and Vial Sizes
Vial size limits for the various classifications of labs
Vial limit Intermediate
Level
(50 x ALI)
ALI
Vial limit Basic Level
Exempt Exempt
estimate (5 x ALI)
Quantity Quantity
(ingestion)
MBq
uCi
MBq/year mCi
MBq
mCi
MBq
H–3
1000
27000
1,000.00
135.00 5,000.00
1350.000
50,000.00
C – 14
100
2700
34.00
4.59
170.00
45.900
1,700.00
P – 32
0.01
0.27
8.00
1.08
40.00
10.800
400.00
P – 33
1
27
80.00
10.80
400.00
108.000
4,000.00
S – 35
100
2700
26.00
3.51
130.00
35.100
1,300.00
Cl – 36
0.01
0.27
20.00
2.70
100.00
27.000
1,000.00
Ca – 45 1
27
20.00
2.70
100.00
27.000
1,000.00
Fe – 59 0.1
2.7
10.00
1.35
50.00
13.500
500.00
I – 125
27
1.00
0.135
5.00
1.350
50.00
Isotope
1
5
Laboratory Signs
1. Rooms containing more than 100 Exempt Quantities of radioisotopes marked with:
a. Radiation Warning Symbol and the words "Radiation Hazard " Contact the RSO
for labels
b. Procedure poster InfolO42I/Revl
c. UW radioisotope permit.
d. Copy of the Current UW Radioisotope Licence.
2. Areas where the radiation field is in excess of 25 mSv/hr (2.5 mR/hr) marked with
a. Radiation Warning Symbol and the words "Radiation Hazard " Contact the RSO
for labels
b. The rate of ionizing radiation in R/hr or Sv/hr.
3. Equipment containing more than 1 Exempt Quantity:
a. Radiation Warning Symbol and the words "Radiation Hazard " Contact the RSO
for labels
b. The name of the radioisotopes.
c. The quantity in Bq or Ci.
d. Contact person.
4. Storage areas where radioisotopes such as refrigerators and freezers are to be marked
with Radiation Warning Symbol and the words "Radiation Hazard " Contact the RSO for
labels
5. Work Areas and radioactive materials, contaminated equipment are to be
clearly identified with radioactive warning tape. (Tape available from Chemistry Stores)
6. Misuse (marking non radioactive material) of radioactive warning tape or signs is a
federal offence.
Dosimetry
Requirements for Dosimetry
1. Both external and internal exposures may be monitored using dosimetry and
bioassays.
2. The following are the dosimetry requirements for the University of Waterloo:
a. Persons working with radioisotopes that are external radiation hazards (i.e. 32P)
will be issued a TLD (Thermal Luminescence Badge).
b. Ring Badges will be worn by radioisotope workers handling more than 50 MBq of
Phosphorous32, Strontium89, Strontium90 or Yttrium90.
c. Neutron dosimetry will be worn by radioisotope workers handling unshielded
neutron sources in excess of 20 GBq.
6
3. Radioisotope workers using 125I or 131I in the following manner must participate in a
bioassay program:
Operation
Maximum
Activity
*Open Bench
5 MBq
Fume Hood
50 MBq
Glove Box (vented)
500 MBq
Involved in a spill
5 MBq
External contamination
any
*Processes which involve the generation of significant quantities of volatile iodine must be
carried out in a fume hood.
4. All records of dosimetry will be kept by the Radiation Safety Officer in the Safety Office
and available for inspection at anytime.
5. The University of Waterloo shall ensure that the effective dose received by and
committed to a person described in the table below (Effective Dose Limits) is not
exceeded. Effective dose is derived from the total dose received from all sources within
the body (i.e. ingested or inhaled radioisotopes plus the doses from external radiation
man made sources and x-rays)
6. Persons expected to receive a dose in excess of 1.0 mSv per year whole body will be
designated as Nuclear Energy Workers (NEW). Workers performing general laboratory
tasks related to university research would not receive a whole body dose in excess of 1
mSv per year and therefore would not be designated as Nuclear Energy Workers.
Effective Dose Limits
Nuclear Energy Worker
Pregnant Nuclear
Energy Worker
Other Workers
One Year
Dosimetry
Period
Five Year
Dosimetry
Period
Balance of
Pregnancy
One Calendar Year
50 mSv
100 mSv
4 mSv
1 mSv
7. The University of Waterloo shall ensure that the equivalent dose received by and
committed to an organ or tissue set out in Table Equivalent Dose Limits is not
exceeded.
Equivalent Dose Limits to Organs
Organ
Nuclear Energy Worker
Other Workers
Lens of eye
150 mSv
15 mSv
Hands and feet
500 mSv
50 mSv
Skin
500 mSv
50 mSv
7
8. Every female nuclear energy worker who becomes aware that she is pregnant shall
immediately inform the University of Waterloo Radiation Safety Officer in writing.
9. The University of Waterloo shall make accommodation to ensure that the effective dose
to the pregnant worker dose does not exceed 4 mSv for the duration of the pregnancy.
10. All workers must apply the ALARA principle when working with radioisotopes to ensure
that they receive the lowest possible dose of ionizing radiation.
Action Levels
1. Any dose exceeding 0.2 mSv will be reported to the worker.
2. Any dose exceeding 0.5mSv the Radiation Safety Officer will::
a. conduct an investigation to determine the magnitude of the dose and to establish
the causes of the exposure;
b. identify and take any action required to prevent the occurrence of a similar
incident; and
c. report the findings to the worker and the Radiation Safety Committee.
3. When the University of Waterloo becomes aware that a dose of radiation received by
and committed to a person or an organ or tissue may have exceeded the dose limits in
table Effective Dose Limits or table Equivalent Dose Limits to Organs. The Radiation
Safety Officer will:
a. immediately notify the worker and the Canadian Nuclear Safety Commission of
the dose;
b. require the person to leave any work that is likely to add to the dose;
c. conduct an investigation to determine the magnitude of the dose and to establish
the causes of the exposure;
d. identify and take any action required to prevent the occurrence of a similar
incident; and
e. within 21 days after becoming aware that the dose limit has been exceeded,
report to the Canadian Nuclear Safety Commission the results of the
investigation or on the progress that has been made in conducting the
investigation; and report the findings to the worker and the Radiation Safety
Committee.
4. If thyroid screening detects more than 10 kBq of I -125 or I -131
a. a preliminary report shall be made immediately to the Canadian Nuclear Safety
Commission
b. have a bioassay performed on the worker with in 24 hours by a person licensed
by the Canadian Nuclear Safety Commission.
c. conduct an investigation to determine the magnitude of the dose and to establish
the causes of the exposure;
d. identify and take any action required to prevent the occurrence of a similar
incident; and
e. report the findings to the Canadian Nuclear Safety Commission, the Radiation
Safety Committee and the worker.
8
Exemption Quantities
Exemption Quantities are the amounts, which if exceeded come under the control of the
Nuclear Safety and Control Act. This quantity is also used to define various regulator criteria.
Exemption Quantities of Various Radioisotopes
Isotope
Quantity Bq
Isotope
Quantity Bq
Isotope
Quantity Bq
1 x 10
5
Niobium 95
1 x 10
5
Americium 241
1 x 10
3
Americium 243
1 x 10
3
Copper 60
1 x 10
5
Nitrogen 13
1 x 10
5
Antimony 124
1 x 10
4
Copper 64
1 x 10
5
Oxygen 15
1 x 10
6
Antimony 125
1 x 10
5
Copper 67
1 x 10
5
Phosphorous 32
1 x 10
4
Arsenic 73
1 x 10
5
Dysprosium 159
1 x 10
6
Phosphorous 33
1 x 10
6
Arsenic 74
1 x 10
4
Erbium 169
1 x 10
6
Polonium 210
1 x 10
4
Arsenic 76
1 x 10
4
Erbium 171
1 x 10
4
Potassium 42
1 x 10
4
Barium 131
1 x 10
5
Fluorine 18
1 x 10
4
Promethium 147
1 x 10
7
Barium 133
1 x 10
5
Gadolinium 153
1 x 10
4
Radium 226
1 x 10
4
Barium 140
1 x 10
4
Gallium 67
1 x 10
6
Rubidium 86
1 x 10
4
Beryllium 7
1 x 10
6
Gallium 68
1 x 10
4
Samarium 153
1 x 10
4
Bismuth 206
1 x 10
5
Germanium 68
1 x 10
4
Scandium 46
1 x 10
5
Bismuth 207
1 x 10
5
Gold 195
1 x 10
5
Scandium 47
1 x 10
5
Bismuth 210
1 x 10
4
Gold 198
1 x 10
4
Selenium 75
1 x 10
5
Bromine 82
1 x 10
5
Hydrogen 3
1 x 10
9
Selenium 79
1 x 10
7
Cadmium 107
1 x 10
7
Indium 111
1 x 10
5
Sodium 22
1 x 10
4
Cadmium 109
1 x 10
6
Indium 113 m
1 x 10
5
Sodium 24
1 x 10
4
Cadmium 113 m
1 x 10
4
Indium 115
1 x 10
5
Strontium 85
1 x 10
5
Cadmium 115
1 x 10
4
Iodine 123
1 x 10
7
Strontium 87 m
1 x 10
5
Cadmium 115 m
1 x 10
4
Iodine 125
1 x 10
6
Strontium 89
1 x 10
4
Calcium 45
1 x 10
6
Iodine 129
1 x 10
6
Strontium 90
1 x 10
4
Calcium 47
1 x 10
4
Iodine 131
1 x 10
4
Sulphur 35
1 x 10
8
Carbon 11
1 x 10
5
Iridium 192
1 x 10
4
Technetium 99
1 x 10
6
Carbon 14
1 x 10
8
Iron 52
1 x 10
4
Technetium 99 m
1 x 10
7
Cerium 139
1 x 10
6
Iron 55
1 x 10
6
Thallium 201
1 x 10
6
Cerium 141
1 x 10
6
Iron 59
1 x 10
5
Thallium 204
1 x 10
4
Cerium 144
1 x 10
5
Krypton 77
1 x 10
10
Thorium 232
1 x 10
2
Cesium 134
1 x 10
5
Krypton 85
1 x 10
11
Tin 113
1 x 10
5
Cesium 134 m
1 x 10
7
Krypton 87
1 x 10
10
Uranium dispersible
1 x 10
4
Cesium 137
1 x 10
4
Lead 210
1 x 10
4
Uranium non-dispersible 1 x 10
7
Chlorine 36
1 x 10
4
Magnesium 28
1 x 10
4
Xenon 123
1 x 10
11
Chlorine 38
1 x 10
4
Manganese 52
1 x 10
5
Xenon 129 m
1 x 10
11
Chromium 49
1 x 10
5
Manganese 54
1 x 10
5
Xenon 133
1 x 10
11
Chromium 51
1 x 10
6
Mercury 203
1 x 10
5
Xenon 135
1 x 10
10
Cobalt 56
1 x 10
5
Molybdenum 99
1 x 10
4
Yttrium 90
1 x 10
4
Cobalt 57
1 x 10
5
Nickel 59
1 x 10
8
Zinc 65
1 x 10
6
Cobalt 58
1 x 10
5
Nickel 63
1 x 10
7
Zirconium 95
1 x 10
5
1 x 10
7
1 x 10
4
Cobalt 58 m
Cobalt 60
Nickel 65
9
Conversion Table
GRAY
1 gray (Gy)
1 milligray (mGy)
1 microgray (µGy)
1 nanogray (ηGy)
RAD
100 rad (rad)
100 millirad (mrad)
100 microrad (µrad)
100 nanorad (η rad)
RAD
1 kilorad (krad)
1 rad (rad)
1 millirad (mrad)
1 microrad (µrad)
GRAY
10 gray (Gy)
10 milligray (mGy)
10 microgray (µGy)
10 nanogray (η Gy)
REM
1 kilorem (krem)
1 rem (rem)
1 millirem (mrem)
1 microrem (µrem)
SIEVERT
1 sievert (Sv)
1 millisievet (mSv)
1 microsievert (µSv)
1 nanosievert (η Sv)
SIEVERT
10 sievert (Sv)
10 millisievet (mSv)
10 microsievert (µSv)
10 nanosievert (η Sv)
REM
100 rem (rem)
100 millirem (mrem)
100 microrem (µrem)
100 nanorem (ηrem)
CURIE
1 kilocurie (kCi)
1 curie (Ci)
1 millicurie (mCi)
1 microcurie (µCi)
1 nanocurie (η Ci)
BECQUEREL
37 tetrabecquerel (TBq)
37 gigbecquerel (Gbq)
37 megabecquerel (MBq)
37 kilobecquerel (kBq)
37 becquerel (Bq)
BECQUEREL
1 tetrabecquerel (TBq)
1 gigbecquerel (GBq)
1 megabecquerel (MBq)
1 kilobecquerel (kBq)
1 becquerel (Bq)
CURIE
27 curie (Ci)
27 millicurie (mCi)
27 microcurie (µCi)
27 nanocurie (ηCi)
27 picocuries (pCi)
10
Contamination Survey Procedures
Method of Measurement
Radioactive contamination may be measured directly or indirectly. Direct measurement means
the use of portable radiation detection instruments to detect both fixed and removable
decontamination. Direct measurement may be used when background radiation levels are
negligible and the detector has sufficient sensitivity. Indirect measurement detects removable
contamination by means of wipe tests but usually have higher sensitivity and will work in areas
with high background. Method of contamination monitoring must be approved by the RSO.
Locations of Measurement
The locations that are to be monitored should be numbered on a plan of the radioisotope work
area. These locations should include working surfaces, such as benches, counter tops, fume
hoods, etc., storage areas, and non-working surfaces such as floors, instruments and
equipment, door handles, light switches, sink taps and telephone receivers. Several random
locations should also be monitored. Too rigid a set of locations may overlook problem areas.
Instrument Checks and Calibration
Non-portable instruments used for counting wipes, such as liquid scintillation counters, wellcrystal type gamma counters, gas-flow proportional counters, semiconductor gamma
spectrometers and gamma cameras, should be routinely serviced according to the
manufacturer's instructions. Keep a record of the service information and dates.
Portable contamination survey meters are checked for efficiency annually by the RSO.
Before monitoring for contamination, portable instruments should be given operational checks
as specified by the manufacturer (i.e. Battery check, high-voltage check, response check, etc.)
And the background radiation level should be measured. Record the operational checks and
background measurement. Similarly, non-portable instruments used to count wipes should
count and record a blank and standard with each set of wipes.
Frequency of Monitoring
Monitoring is to be completed at least once per week when working with radioisotopes. The
Contamination Survey Forms are to be completed and available at all times for inspection by
the RSO and CNSC.
Your work area should be surveyed with a survey meter during and at the end of each workday
or work period(note: low energy Beta emitters such as 3H can not be monitored using a survey
meter). This ensures that radioactive contamination is not inadvertently spread about or taken
home. The results of these surveys do not have to be recorded.
11
Direct Measurement of Contamination
Depending upon the detector and the radioisotopes, direct measurement is often convenient
for monitoring large areas. Direct measurement instrument readings include both fixed and
non-fixed contamination. Thus a reading, which satisfies the licence criteria, gives a
conservative estimate of non-fixed contamination.
1. Monitor the locations marked on the plan of the working area by slowly passing the
detector over each area.
2. Keep the detector face towards the surface being monitored and keep the distance
between the detector and the surface as small as possible without touching (and
possible contaminating) the detector.
3. If contamination is detected, stop and obtain a measurement. Clean the area until the
instrument is below the licence criteria. A reading in excess of licence criteria after
repeated cleaning is an indication of fixed contamination or a high radiation
background.
4. Identify and mark the contaminated area on the plan.
5. Record the highest measurement for each area and the final measurement after
decontamination.
Calculating Fixed Contamination
The readings from contamination metres can be related to regulatory criteria if the efficiency of
the instrument for a specific radioisotope is known. For mixtures of radioisotopes, do all
calculations using the radioisotope for which the instrument has the lowest detection efficiency.
Using the following equation, calculate the measurement results in Bq/cm2
WHERE:
N = is the total count rate in counts per minute (CPM) measured directly or on the wipe.
Nb = is the normal background count rate (in CPM) from the survey instrument.
E = is the instrument efficiency factor (expressed as a decimal, i.e. for 26% efficiency, E =
0.26) for the radioisotope being measured. Efficiency for each isotope is determined by the
RSO
60 = sec/min
A = area or the detector in cm2
12
Indirect Measurement of Contamination
Indirect measurement of contamination is used when portable instruments are not sensitive
enough or when the radiation background is too high. Indirect methods can only be used to
monitor non-fixed or removable contamination. This is the most common method of
contamination measurement used at the University of Waterloo.
1. Wear protective disposable gloves and a lab coat.
2. Wipe each of the locations shown on the plan of the working area with a filter paper
lightly moistened with alcohol or water. Use one numbered wipe per location. One
"screening" wipe can be used to monitor several locations. If contamination is found, the
areas must be identified and decontaminated.
3. Wipe an area of 100 cm2. Using uniform and constant pressure, ensure the entire area
is wiped.
4. If necessary, carefully dry the wipe to prevent loss of activity. Since the contamination
may be absorbed into the wipe material, the use of a wetting agent may lead to a
significant underestimate of alpha and low-energy beta (3H) contamination with some
counting methods.
5. Count the wipes in a low-background area and record all results.
6. If the wipes are to be counted on a contamination meter, the wipe should be smaller
than or equal to the sensitive area of the detector.
7. Record results on a contamination monitoring form before and after decontamination.
8. Clean any contaminated areas and re-monitor.
Calculating Removable Activity
The readings from non-portable instruments can be related to regulatory criteria if the
efficiency of he instrument for a specific radioisotope is known. For mixtures of radioisotopes,
do all calculations using the radioisotope for which the instrument has the lowest detection
efficiency.
Using the following equation, calculate the measurement results in Bq/cm2
WHERE:
N = is the total count rate in counts per minute (CPM) measured directly or on the wipe.
Nb = is the count rate of the blank (in CPM)
E = is the instrument efficiency factor (expressed as a decimal, i.e. for 26% efficiency, E =
0.26) for
the radioisotope being measured (consult the manufacturer)
60 = sec/min
A = area wiped (not to exceed 100 cm2)
F = is the collection factor for the wipe . Use a value of F = 0.1 (i.e., 10%).
13
Instrument Selection
Instrument selection for weekly wipe tests is to be approved by the RSO.
Beta Contamination Survey Meters (GM Meters)
All radioisotope laboratories except those using exclusively 3 H or 63 Ni will have available a
functioning survey meter. Most laboratories will use a GM meter with a pancake type probe.
These GM type (Geiger Muller) meters are useful for detecting the spread of contamination but
are not sensitive enough to detect low energy beta emitters below regulatory levels. This type
of meter must not be used as a dose meter for gamma radiation or X-rays.
Meters are to be tested by the RSO annually. They will be marked with the following:
GM Survey Meter
Beta Counting Efficiency
Energy
160 keV
Efficiency 10%
300 keV
33%
1.17 keV
47%
Do not use mR/hr Scale
Date_________
UW Safety Office
Gamma Survey Meters
These meters are to be sent away annually for calibration. A gamma dose rate meter is
available at the Safety Office.
Liquid Scintillation Counters
Liquid scintillation counters are generally acceptable for most contamination monitoring. Their
higher efficiency, low background and multiple sample counting makes them ideal for
contamination survey work. Liquid Scintillation counters will easily meet regulator criteria for
detection radioactive contamination.
14
Contamination Monitoring Records
Contamination monitoring records are used to audit a laboratories contamination control
program. Monitoring records are a licence requirement and must be legible, complete and
available for inspection by the RSO or CNSC at all times.
Radiation Contamination Survey Forms are available from the RSO (Ian Fraser Ext 6268) or
by downloading the forms as a PDF file Radiation Contamination Survey Forms from the
"FORMS" section of the Radiation Safety Page.
Below is an example of a completed contamination survey form.
RADIATION CONTAMINATION SURVEY FORM
BUILDING___HS____
ROOM___125_____ SURVEY EQUIPMENT Packard 7500 LSC
Name Ian Fraser
Date Nov. 27, 2000
AR
CPM Bg/cm2
EA
1
45
Name Ian Fraser
Date Nov. 27, 2000
AREA
CPM
Bg/cm2
Name
Date
AREA
1
1
2
44
2
2
3
53
3
3
4
42
4
4
5
61
5
5
6
6
6
7
7
7
8
1894
9.4
2
8
45
2
CPM
Bg/cm2
8
9
9
9
10
10
10
11
11
11
12
12
12
Bkg 42
Bkg
44
Bkg
Notes:
1. Wipe areas and equipment that has been used that week. Also do one or two random
areas.
2. If contamination in area or equipment is above regulatory limits, clean and re-wipe.
Place results in next row.
15
Regulatory Limits of Contamination
Minimum Levels of Contamination
1. For control areas, removable surface contamination limit criteria averaging over an area
not exceeding 100 cm2 are as follows:
a. 0.3 Becquerel per square centimeter averaged over an area not to exceed 100
square centimeters for all Class A Radionuclides;
b. 3 Becquerel per square centimeter over an area not to exceed 100 square
centimeters for all Class B Radionuclides and
c. 30 Becquerel per square centimeter over an area not to exceed 100 square
centimeters for all Class C Radionuclides.
2. For supervised public areas and for decommissioning, removable surface contamination
limit criteria averaging over an area not exceeding 100 cm2 are as follows:
a. 0.3 Becquerel per square centimeter averaged over an area not to exceed 100
square centimeters for all Class A Radionuclides;
b. 3 Becquerel per square centimeter over an area not to exceed 100 square
centimeters for all Class B Radionuclides and
c. 30 Becquerel per square centimeter over an area not to exceed 100 square
centimeters for all Class C Radionuclides.
3. The dose rate due to fixed contamination does not exceed 0.5 mSv at 0.5 meter from
any surface.
Frequency of Contamination Monitoring
Contamination monitoring must be done as follows:
1. Basic Laboratories at least weekly
2. Intermediate laboratories at least weekly
3. High level Laboratories at least daily
4. After a spill or incident
5. Before equipment is released for non-radioactive use
6. Before decommissioning room for non-radioactive work
Records
Records of all contamination measurements shall be maintained and available for inspection
by the RSO or the C.N.S.C. for at least 3 years.
16
Classification of Radionuclides
Class A Radionuclides
Na-22
Na-24
Co-60
Zn-65
Ir-192
Ta-182
All Alpha Emitter and their daughter isotope
Class B Radionuclides
As-74
Fe-59
Au-198
Ga-67
Br-82
Gd-153
Co-58
Hg-203
F-18
I-131
In-111
In-114m
Nb-95
Rb-84
Rb-86
Sc-46
Se-75
Sm-153
Sn-113
Sn-123
Sb-124
Sr-85
Sr-90
Class C Radionuclides
Au-195m
Cl-36
Kr-81m
Re-188
TI-201
C-14
Co-57
Nb-98
Ru-103
Xe-127
Ca-45
Cr-51
Ni-63
S-35
Xe-133
Cd-109
H-3
P-32
Sr-89
Y-90
Ce-133
I-123
P-33
Tc-99
Yb-169
Ce-144
I-125
Re-186
Tc-99m
Note: Most commonly used radioisotopes used at UW are Class C.
17
Decontamination Procedures for Areas and Equipment
HEPA Vacuum
High efficiency vacuum cleaning is good on dry porous surfaces and avoids water reactions.
All dust must be filtered out using only HEPA filters and the machine is left contaminated.
Hot Water and Detergent
For spills covering small areas blot up liquid and rinse with hot water and detergent. Hot
water and detergent may be used on glassware and clothing if immersed and agitated. This
method is extremely effective if done immediately after the spill on a non-porous surface, but is
ineffective for decontaminating large areas or long standing contamination.
Decon 75 or Alconox
Complexing agents are very effective on nonporous surfaces. To use make a solution of 3%
complexing agent with water, spray surface with solution, keep moist for 30 minutes. Remove
solution and rinse. Smaller objects can be immersed in solution. Complexing agents keep
contamination in solution, are non-toxic and very effective but require long soaking time (30
minutes) and have little penetration power.
Organic Solvents
Contaminated organic material (oil, paint etc.) can be dissolved by immersion or applying
solvent to the surface, and then blotting up the liquid and wiping clean. This method requires
good ventilation because most solvents are flammable and toxic.
Inorganic Acids
Contaminated metal and deposits on porous surfaces can be decontaminated using inorganic
acids. Immerse smaller objects or brush on in a 1-2 N acid solution then flush with water. The
material must then be scrubbed with detergent water mixture and rinsed. Acids may cause
excessive corrosion and are hazardous to skin and eyes.
Abrasion (Old Dutch Steel Wool)
Nonporous surfaces can be decontaminated using abrasives by abrading the surface. Apply
abrasive to surface and rub then rinse with water. Use on non-porous surfaces.
18
Ordering Radioisotopes
1. Fill out a Purchase Requisition (Systems Contract Orders will not be processed) and
include:
a. UW internal permit number
b. quantity in Bq or Ci
c. Radioisotope.
2. Orders are not to exceed quantities or isotopes specified on UW internal permit.
3. Send Purchase Requisition to the Purchasing Department.
4. The Radiation Safety Officer (RSO) reviews orders for approval.
5. When ordering "equipment" which contains a radioisotope, state this fact on the
purchase order and provide information as noted above.
Receiving
1. All persons receiving radioactive material must successfully complete the UW
Transportation of Radioactive Material Training Course.
2. If upon receipt of a package containing radioactive material there is :
a. noticeable damage to the package
b. leakage from the package
c. packages without a UW Purchase Order
d. mislabeled packages
3. Central Stores receiving personal will immediately notify
UW Radiation Safety Officer
Ian Fraser Ext 6268
If unavailable notify UW Police 4911
4. All goods marked with radioactive material labels are to be transferred to Greg Friday
ESC Rm. 150.
5. On receipt of radioisotopes the contents are checked for leakage by the RSO/designate.
6. Any leakage will be reported immediately to the CNSC by the RSO.
7. The following sections of an inventory form will be completed by the RSO/designate:
a. Permit Holder
b. Isotope
c. Quantity
d. Lot Number
e. Material
f. Date Received
g. Vial id, if there are 2 or more vials with the same lot number
h. Record of package contamination monitoring
8. Radioisotopes will be delivered with the inventory form directly to or picked up by the
permit holder/designate.
9. A record of receipt will be maintained br the RSO/designate.
10. The permit holder shall:
a. Store the radioisotopes in a secure area(locked refrigerator, freezer or cabinet).
b. Remove the inventory form from the package and make it available for
inspection.
11. If package is not checked for leaks by the RSO/designate, the contents must be
checked for leakage by the permit holder. Any leakage is to be reported immediately to
the RSO (Ext. 6268)
19
Inventory
1. When a package is received remove the inventory form from the package and place in
your record book.
2. If no inventory form comes with the package, contact the RSO, check the package for
contamination and start an inventory form yourself.
3. UW inventory forms must be kept up to date and available for inspection by the RSO or
the CNSC. Information to include:
a. Amount of radioisotope used
b. User's initials
c. Wipe test date
d. Waste information
e. Final disposal information
UNIVERSITY of WATERLOO RADIOISOTOPE INVENTORY
Isotope: ______32 P______
Location ___HS 125____
Date Received (D/M/Y):__18/12/99______
Supervisor: __Fraser_______
Material: __CTP_ Lot #: ____Ad99Cxs______
Permit #: ___54___
Activity (mCi): _0.25_____
Vial Id:_______
Volume (μL): ___125____
Date Used
User Wipe Test
Amount Type of
Wast
% of material
Initia Date
Used
Waste
e
in each waste
ls
Strea
stream
(μL)
m
Jan. 23,
Jan. 26/2001
25
L
2
10
2001
L
3
90
S
3
100
Jan.29,2001
Feb.2, 2001
45
L
2
10
L
3
90
S
3
100
Remainder
to waste Feb
16, 20001
Type of Waste
Waste Stream
L= Aqueous
1=Municipal Garbage
O= Organic
2= Municipal Sewer
S=Solid
3=U W Environmental Safety Facility
A= Animal Carcass
4= Other (specify)
Package Contamination___None Detected__ Signature___Ian Fraser___ PO No._43994_
20
Disposal of Radioisotopes
Disposal limits for radioisotopes insure that no member of the public is exposed to any
significant quantities of radioisotopes.
Liquid Waste
1. Liquid waste is to be separated according to isotope, placed in a 4L Jug supplied by the
Environmental Safety Facility (ESF).
2. Containers must not be more than 80% full.
3. No solid waste in the containers.
Containers are to be marked with a Radioactive Waste Label.
Solid Waste
1. Solid waste is to be separated according to isotope, placed in a 20 L Pails lined with a 6
mil poly bag supplied by the Environmental Safety Facility (ESF).
2. Containers must be closed tightly
3. No liquid waste in the containers.
4. Containers are to be marked with a Radioactive Waste Label.
5. Solid waste less than limits listed in table below may be disposed of in regular garbage.
Scintillation Vials
1. Scintillation vials are to be placed in a 20 L Pails lined with a 6 mil poly bag supplied by
the Environmental Safety Facility (ESF). Vials can be of any isotopes.
2. Pails must be closed tightly
3. Containers are to be marked with a Radioactive Waste Label.
Disposal Limits
Radionuclide Solid Waste
Solid Waste
MBq/kg
uCi/kg
Liquid Waste
MBq/L
Liquid Waste
uCi/L
C-14
Cr-51
Fe-59
H-3
I-125
I-131
P-32
P-33
S-35
0.37
0.37
0.001
3.7
0.0037
0.0037
0.01
1
0.037
10
10
0.027
100
0.1
0.1
0.27
27
1
3.7
3.7
307
37
0.037
0.037
0.37
1
0.37
100
100
100
1000
1
1
10
27
10
21
General Laboratory Procedures
1. Keep laboratory locked when unattended.
2. All radioisotopes must be stored in a locked cabinet, refrigerator or freezer.
3. Keep active and inactive work separated as far as possible.
4. Mark radioactive work area and equipment with radioactive label tape.
5. Work over a spill tray lined with absorbent paper and in a fume hood or glove box when
working with dry powders or volatile substances.
6. Fume hood sash must be no higher than use indicator arrow.
7. Fume hoods are to be tested annually.
8. Use a flow indicator to insure that the fume hood is operational.
9. Mark storage areas with radioactive labels.
10. Use the minimum quantity of radioactivity possible.
11. Wear protective clothing, safety glasses and gloves when handling radioactivity.
12. Remove gloves, wash hands and monitor yourself and your work area before leaving an
active area.
13. Label containers of radioactive material clearly, indicating nuclide, total activity, date
and the level of radiation at the surface of the container.
14. Never eat, drink, smoke or apply cosmetics in an area where unsealed radioactivity is
handled.
15. Never work with unprotected cuts or breaks in the skin.
16. Never pipette radioactive solutions by mouth.
17. In order to assist the R.S.O. in exchanging TLD badges, please store them in a central
location when not in use.
18. To minimize the dose to the extremities, tongs or other remote handling equipment
should be used where appropriate.
19. Contamination monitoring must be done at least once per week while working with
radioisotopes. Records must be maintained and available for inspection.
20. Inventories of all radioisotopes must be carefully maintained and available for
inspection.
21. Glassware and equipment used for radioactive work must be segregated until it has
been decontaminated.
22
Emergency Contacts
Radiation Safety Officer
•
work
o On Campus Ext. 6268
o Off campus (519) 8884567 Ext. 6268
•
•
home (519) 884-6354
if unavailable contact UW Police
o On Campus Ext. 4911
o Off campus(519) 888-4911
Permit Holder
Permit holders home phone number is located on the Radioisotope Permit
23
Emergency Procedures Spills
General Precautions
1. Inform persons in the area that a spill has occurred. Keep them away from the
contaminated area.
2. Cover the spill with absorbent material to prevent the spread of contamination.
Minor Spills (less than 1 Exempt Quantities)
1. If you feel comfortable in cleaning up the spill proceed, if not, contact the RSO for help.
2. Limit movement near the spill.
3. Put on 2 pairs of disposable gloves, lab coat and respiratory protection if required.
4. Mark the location of the spill with a wax pencil and begin approved decontamination
procedures as soon as possible.
5. Place absorbent paper on spill if wet
6. If spill is a powder, wet with water/organic solvent and place absorbent paper on wetted
material.
7. To avoid spreading the contamination, work from the outside of the spill towards the
centre.
8. Do not track contaminants away from the spillage area.
9. Place contaminated absorbent paper in sealable container and label.
10. Following decontamination, check the area for any residual contamination. Repeat
decontamination, if necessary, until contamination-monitoring results meet the
radioisotope licence criteria. If the spill cannot be cleaned up call the Radiation Safety
Officer at Ext. 6268 or contact UW Police Ext. 4911.
11. Report the spill and cleanup to the supervisor and the Radiation Safety Officer at Ext.
6268.
12. Record spill details, contamination-monitoring results and adjust inventory records.
Major Spills (More than 1 Exempt Quantities)
1. Clear the room. Persons not involved in the spill clean up should be prevented entry.
2. Call the Radiation Safety Officer at Ext.6268 ( do not leave a voice mail message). If
not in, contact UW Police at Ext. 4911.
3. Limit the movement of all personnel who may be contaminated until they are monitored.
4. Leave the fume hood running to minimize the release of volatile radioactive materials
into adjacent rooms and hallways.
5. Close off and secure the spill area to prevent entry. Post warning signs.
24
Contaminated Personnel
Contact Radiation Safety Officer at Ext. 6268 or UW Police at Ext. 4911.
Scan with survey metre to determine contaminated body areas.
1. If skin appears to be intact:
a. wet hands and apply mild soap
b. work up good lather, keep lather wet
c. work lather into contaminated area by rubbing gently for 3 minutes
d. rinse thoroughly with lukewarm water
e. repeat above procedures twice, if necessary
2. If cuts, abrasions, or open wounds are observed:
a. obtain medical assistance through the Radiation Medical Advisor
b. dry clean the effected area with suction and swabs
c. if skin is contaminated in the area of cuts, abrasions, or open wounds, use wet
swabs in a direction away from the area, taking care not to spread activity over
body or into wound
3. If ingestion has occurred:
a. obtain medical advice and/or assistance immediately from the Radiation Medical
Advisor
Release of Airborne Radioisotopes
1. If possible, cut off the release of radioactive material from the source into the
environment.
2. Close windows and any doors to other areas, call Plant Operations to place building on
100% fresh air (Ext. 3793).
3. Contact Radiation Safety Officer at Ext. 6268 or UW Police Ext. 4911.
4. Evacuate personnel and prevent further personnel access to radiation area by closing
and locking doors.
5. Monitor all persons who may be contaminated and determine which persons may have
been exposed to external radiation and/or inhalation of radionuclides and to what
degree.
6. Perform simple decontamination and obtain medical assistance promptly from the
Radiation Medical Advisor.
7. The Radiation Safety Officer will submit a report if required to the C.N.S.C..
25
Tritium Data Sheet
Physical Characteristics
Isotope 3H
Half Life 12.26 Years
Mode of Decay Beta 100%
Energy Maximum 0.0186 MeV
Average 0.0057 MeV
Decay Product 3He
Biological Data
Biological Half Life 30 Days
Effective Half Life 12.0 Days
Target Organ Body Fluids
Legislative Limits
Exempt Quantity 1000 MBq (27 mCi)
ALI Ingestion 1000 MBq (27 mCi)
Sewage discharge (institutional Limit) 1,000,000
MBq/yr (2,7000 mCi/yr)
Sewage discharge (laboratory limit) 3.7 MBq/L
(100 uCi/L)
Landfill discharge 37 MBq/kg (1.0 mCi/Kg)
Shielding Data
Maximum range in air 6 mm
Maximum range in water 6 x103
mm
Shielding required None
Dose Rate from External Exposures
Contamination
The low energy Beta particle emitted by tritium is not an Monitoring Method
external radiation hazard, as it can not penetrate the skin
Liquid scintillation
or travel very far in air.
Dose from Skin Contamination
Limits of Contamination
Uniform Deposit 1 kBq/cm2 = 0 mSv/hr
Controlled Areas = 300 Bq/cm2
0.05 ml droplet 1 kBq = 0 mSv/hr
Uncontrolled Areas = 30
External Dose form a 1 MBq Source in:
Bq/cm2
Point source at 30 cm = 0 mSv/hr
10 ml glass vial at 100 cm = 0 mSv/hr
Contact with 5ml plastic syringe = 0 mSv/hr
Notes:
Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an
organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much
longer. Consider tritium as an example: tritiated water has an effective biological half-life of 12 days whereas tritiated thymidine
has a 190 day half life.
ALI is defined as the Annual Limit of Intake by ingestion or inhalation which would produce a dose of 20 mSv .
Handling Procedures
1.
2.
3.
4.
Disposable gloves and lab coat should be worn when handling 3H.
Use a spill tray and absorbent paper to contain spills.
Handle potentially volatile compounds in ventilated enclosures.
Bioassay must be done if 3H is used as follows :
Operation
Tritiated Water
Nucleic Acid Precursors
Tritiated compounds
Open Bench 400 MBq (10 mCi)
400 MBq (10 mCi)
4 GBq(100 mCi)
Fume hood
2 GBq (54 mCi)
20 GBq(540 mCi)
700 MBq (19 mCi)
26
Carbon 14 Data Sheet
Physical Characteristics
Isotope 14C
Half Life 5730 Years
Mode of Decay Beta 100%
Energy Maximum 0.356 MeV
Average 0.049 MeV
Decay Product l4N
Biological Data
Biological Half Life 12.0 Days
Effective Half Life 10.0 Days
Target Organ Fatty Tissue
Legislative Limits
Exempt Quantity 100 MBq (2.7 mCi)
ALI Ingestion 34 MBq (0.9 mCi)
Sewage discharge (institutional Limit) 10,000
MBq/yr ( 270 mCi/yr)
Sewage discharge (laboratory limit) 0.37
MBq/L(10 uCi/L)
Landfill discharge 3.7 MBq/kg (100 uCi/L)
Shielding Data
Maximum range in air 24 cm
Shielding required None
Dose Rate from External Exposures
Contamination Monitoring Method
Liquid scintillation
The low energy Beta particle emitted by tritium is not
Geiger Counter
an external radiation hazard, as it can not penetrate the Limits of Contamination
skin or travel very far in air.
Controlled Areas = 300 Bq/cm2
Dose from Skin Contamination
Uncontrolled Areas = 30 Bq/cm2
2
Uniform Deposit 1 kBq/cm = 3.2 10-1 mSv/hr
0.05 ml droplet 1 kBq = 2.7X 10-3 mSv/hr
External Dose form a 1 MBq Source in:
Point source at 30 cm = 0 mSv/hr
10 ml glass vial at 100 cm = 0 mSv/hr
Contact with 5ml plastic syringe = 0 mSv/hr
Notes:
Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an
organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much
longer.
ALI is defined as the Annual Limit of Intake by ingestion or inhalation which would produce a dose of 20 mSv .
Handling procedures
1.
2.
3.
4.
Disposable gloves and lab coat should be worn when handling.
Use a spill tray and absorbent paper to contain spills.
Use extra caution when handling l4C labeled nucleic acid or their precursors.
All work with labeled l4C solvents or materials with a low boiling point must be done in a
fume hood.
27
Phosphorous 32 Data Sheet
Physical Characteristics
Isotope 32P
Half Life 14.28 Days
Mode of Decay Beta 100%
Energy Average 0.7 MeV
Maximum 1.710 MeV
Decay Product 32S
Biological Data
Biological Half Life 257 Days
Effective Half Life 13.5 Days
Target Organ Bone
Legislative Limits
Exempt Quantity 0.01 MBq (0.27 uCi)
ALI Ingestion 8 MBq(216 uCi)
Sewage discharge (institutional Limit) 1 MBq/yr (27
uCi)
Sewage discharge (laboratory limit) 0.0037
MBq/L(0.1 uCi/L)
Landfill discharge 0.037 MBq/kg (1 uCi/Kg)
Shielding Data
Maximum range in air 6 m
Shielding required 1 cm
plexiglass
Dose Rate from External Exposures
Contamination Monitoring Method
The high energy Beta particle emitted by Phosphorous 32
Liquid scintillation
is an external radiation hazard, close contact will add
Geiger Counter
significantly to total dose.
Limits of Contamination
Dose from Skin Contamination
Controlled Areas = 300 Bq/cm2
Uniform Deposit 1 kBq/cm2 = 1.9 mSv/hr
Uncontrolled Areas = 30 Bq/cm2
0.05 ml droplet 1 kBq =1.3 mSv/hr
External Dose form a 1 MBq Source in:
Point source at 30 cm = 0.12 mSv/hr
10 ml glass vial at 100 cm = 1.30 mSv/hr
Contact with a 50 ml glass beaker = 7.1 X 10-4
mSv/hr
Contact with 5ml plastic syringe = 240 mSv/hr
ALI is defined as the Annual Limit of Intake by ingestion which would produce a dose of 20 mSv .
Precautions
1. Phosphorus 32 is the highest radionuclide commonly encountered in research
laboratories and as such requires special care.
2. Disposable gloves and lab coat should be worn when handling.
3. Use a spill tray and absorbent paper to contain spills.
4. Double glove ( all direct contact with 32P must be avoided).
5. Safety glasses or Plexiglas shielding are to be used if handling quantities in excess of
37 MBq.
6. Finger Badges are to worn if handling quantities in excess of 50 MBq.
7. Remote handling devices (tongs etc.) should be used when handling amounts of more
than 37 MBq.
8. Use syringe or pipette shields when manipulating stock solutions in excess of 37 MBq.
9. The use of low density shielding should be used to minimize the production of gamma
radiation (Bremsstrahlung). Some lead shielding may be required in addition to
Plexiglas when tens of millicuries are used.
10. After each use the worker and area must be monitored using a Geiger-Mueller counter.
28
Phosphorous 33 Data Sheet
Physical Characteristics
Isotope 33P
Half Life 25.6 Days
Mode of Decay Beta 100%
Energy Average 0.076 MeV
Maximum 0.249 MeV
Decay Product 33S
Biological Data
Biological Half Life 257 Days
Effective Half Life 13.5 Days
Target Organ Bone
Legislative Limits
Shielding Data
Exempt Quantity 1 MBq (27 uC1)
Maximum range in air 46 cm
ALI Ingestion 80 MBq (2.2 mCi)
Shielding required non
Sewage discharge (institutional Limit) 10 MBq/yr
(270 uCi/yr)
Sewage discharge (laboratory limit) 0.1
MBq/L(2.7 uCi/L)
Landfill discharge 1 MBq/kg (27 uCi/Kg)
Dose Rate from External Exposures
Contamination Monitoring Method
Liquid scintillation
Low energy Beta particle emitted by Phosphorus 33 is
Geiger Counter
not an significant external radiation hazard, as it can
Limits of Contamination
not penetrate the skin or travel very far in air.
Controlled Areas = 300 Bq/cm2
Dose from Skin Contamination
Uncontrolled Areas = 30 Bq/cm2
Uniform Deposit 1 kBq/cm2 = 0.86 mSv/hr
0.05 ml droplet 1 kBq =0.14 mSv/hr
External Dose form a 1 MBq Source in:
Point source at 30 cm = 0 mSv/hr
10 ml glass vial at 100 cm = 0 mSv/hr
Contact with a 50 ml glass beaker = 0 mSv/hr
Contact with 5ml plastic syringe = 0 mSv/hr
Notes:
Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an
organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much
longer. ALI is defined as the Annual Limit of Intake by ingestion which would produce a dose of 20 mSv .
Precautions
1. Disposable gloves and lab coat should be worn when handling.
2. Use a spill tray and absorbent paper to contain spills.
3. Handle 33 P compounds that are potentially volatile or in powder form in ventilated
enclosures.
29
Sulfur 35 Data Sheet
Biological Data
Biological Half Life 90.0 Days
Effective Half Life 44.3 Days
Target Lungs
Physical Characteristics
Isotope 35S
Half Life 87.9 Days
Mode of Decay Beta 100%
Energy Maximum O. 167 MeV
Average 0.049 MeV
Decay Product 35Cl
Legislative Limits
Shielding Data
Exempt Quantity 100 MBq (2.7 mCi)
Maximum range in air 30 cm
ALI Ingestion 26 MBq (0.7 mC1)
Shielding required None
Sewage discharge (institutional Limit) 1000
MBq/yr (27 mCi/yr)
Sewage discharge (laboratory limit) 0.037 MBq/L
(1 uCi/L)
Landfill discharge 0.37 MBq/kg (10 uCi/kg)
Dose Rate from External Exposures
Contamination
Monitoring Method
Low energy Beta particle emitted by Sulfur 35 is not an
Liquid scintillation
external radiation hazard, as it can not penetrate the
Geiger Counter
skin or travel very far in air.
Limits of Contamination
Dose from Skin Contamination
Controlled Areas = 300 Bq/cm2
Uniform Deposit 1 kBq/cm2 = 3.5 10-1 mSv/hr
Uncontrolled Areas = 30 Bq/cm2
0.05 ml droplet 1 kBq = 4.1X 10-3 mSv/hr
External Dose form a 1 MBq Source in:
Point source at 30 cm = 0 mSv/hr
10 ml glass vial at 100 cm = 0 mSv/hr
Contact with a 50 ml glass beaker = 0 mSv/hr
Contact with 5ml plastic syringe = 0 mSv/hr
Notes:
Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an
organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much
longer. ALI is defined as the Annual Limit of Intake by ingestion or inhalation which would produce a dose of 20 mSv .
Handling Procedures
Disposable gloves and lab coat should be worn when handling 35S.
Disposable gloves and lab coat should be worn when handling.
Use a spill tray and absorbent paper to contain spills.
Radio-lysis of 35S radiolabeled compounds may occur during storage, causing the
release of volatile 35S compounds. Vials should be opened only in fume hoods.
5. Radio-lysis may also occur during heating. Insure that all processes which heat 35S
compounds are done in a fume hood.
1.
2.
3.
4.
30
Calcium 45 Data Sheet
Physical Characteristics
Isotope 45Ca
Half Life 165 Days
Mode of Decay Beta 100%
Energy Maximum 0.252 MeV
Average 0.76 MeV
Decay Product 45Sc
Biological Data
Biological Half Life 1.8 x 104 Days
Effective Half Life 162 Days
Target Organ Bone
Legislative Limits
Exempt Quantity 1 MBq
ALI Ingestion 26 MBq
Shielding Data
Maximum range in air 48 cm
shielding required none
Dose Rate from External Exposures
Dose rates are not given for the week Beta emitters
such as 45Ca because such figures are negligible in
most practical circumstances. Dose from these
radionuclides is only important when the activity is
ingested, or when on direct contact with the skin.
Dose from Skin Contamination
Uniform Deposit 1 kBq/cm2 = 0.84 mSv/hr
0.05 ml droplet 1 kBq = 0.1 mSv/hr
External Dose form a 1 MBq Source in:
Point source at 30 cm = 0 mSv/hr
10 ml glass vial at 100 cm = 0 mSv/hr
Contact with a 50 ml glass beaker = 0 mSv/hr
Contact with 5ml plastic syringe = 0 mSv/hr
Notes:
Contamination
Monitoring Method
Liquid Scintillation
Geiger Counter
Limits of Contamination
Controlled Areas = 300 Bq/cm2
Uncontrolled Areas = 30 Bq/cm2
Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an
organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much
longer. ALI is defined as the Annual Limit of Intake by ingestion which would produce a dose of 20 mSv .
Handling Procedures
1. Disposable gloves and lab coat should be worn when handling 45Ca.
2. Use a spill tray and absorbent paper to contain spills.
3. Use extra caution when handling 45Ca due to its high affinity for bone tissue. Its long
biological half life could result in damage to blood producing tissues within the bone.
31
Chromium 51 Data Sheet
Physical Characteristics
Isotope 51Cr
Half Life 27.7 Days
Mode of Decay XRAY Gamma and Auger
Electrons
Energy X-Ray 0.005 MeV 22.3%
Gamma 0.320 MeV 9.8%
Auger Electrons 0.004 MeV 66.9%
Decay Product 51 V
Biological Data
Biological Half Life 616 Days
Effective Half Life 26.6 Days
Target Organ Lungs
Legislative Limits
Shielding Data
Exempt Quantity 1 MBq (27 uCi)
Half Value Layer of Lead =
ALI Ingestion 530 MBq (14.32 mCi)
1.7mm
Sewage discharge (institutional Limit) 100 MBq/yr
(2.7 mCi/yr)
Sewage discharge (laboratory limit) 0.37 MBq/L
(10 uCi/L)
Landfill discharge 3.7 MBq/kg (100 uCi/kg)
Dose Rate from External Exposures
Dose from Skin Contamination
Uniform Deposit 1 kBq/cm2 = 1.5 X 10-2 mSv/hr
0.05 ml droplet 1 kBq = 5.7 X 10-4 mSv/hr
External Dose form a 1 MBq Source in:
Point source at 30 cm
Skin =0 mSv/hr
Deep tissue= 6 X10-5 mSv/hr
10 ml glass vial at 100 cm = 5.4 X10-6 mSv/hr
Contact with a 50 ml glass beaker = 1.92 X102mSv/hr
Contact with 5ml plastic syringe = 8.7 X10-2
mSv/hr
Notes:
Contamination
Monitoring Method
Liquid Scintillation
Crystal Scintillation
Geiger Counter
Limits of Contamination
Controlled Areas = 300 Bq/cm2
Uncontrolled Areas = 30 Bq/cm2
Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an
organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much
longer. ALI is defined as the Annual Limit of Intake by ingestion which would produce a dose of 50 mSv .
Handling Procedures
Disposable gloves and lab coat should be worn when handling 51Cr.
Use spill tray and absorbent material.
Use of lead shielding is required when handling quantities in excess of 37 MBq.
Remote handling devices (tongs etc.) should be used when handling quantities in
excess of 37 MBq.
5. Use syringe or pipette shields when manipulating stock solutions in excess of 37 MBq.
1.
2.
3.
4.
32
Iron 59 Data Sheet
Physical Characteristics
Isotope 59Fe
Half Life 45.60 Days
Mode of Decay Beta and Gamma
Energy Beta 0.478 MeV 53%
0.281 MeV 45%
Gamma 1.095 MeV 55%
MeV 43%
Decay Product 59Co
Biological Data
Biological Half Life 600 Days
Effective Half Life 42.0 Days
Target Organ Spleen
Legislative Limits
Shielding Data
Exempt Quantity 0.1 MBq (2.7 uCi)
Half Value Layer Lead 10mm
ALI Ingestion 10 MBq (270 uCi)
Sewage discharge (institutional Limit) 1 MBq/yr (27
uCi/yr)
Sewage discharge (laboratory limit) 0.001
MBq/L(0.027 uCi/L)
Landfill discharge 0.01 MBq/kg (0.27uCi/kg)
Dose Rate from External Exposures
Dose from Skin Contamination
Uniform Deposit 1 kBq/cm2 = 0.97 mSv/hr
0.05 ml droplet 1 kBq = 0.3 mSv/hr
External Dose form a 1 MBq Source in:
Point source at 30 cm
Skin =0.037 mSv/hr
Deep tissue= 1.9 X 10-3
10 ml glass vial at 100 cm = 1.6 10-4 mSv/hr
Contact with a 50 ml glass beaker = 0.58 mSv/hr
Contact with 5ml plastic syringe = 2.7 mSv/hr
Contamination
Monitoring Method
Liquid Scintillation
Crystal Scintillation
Geiger Counter
Limits of Contamination
Controlled Areas = 300 Bq/cm2
Uncontrolled Areas = 30 Bq/cm2
Notes:
Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an
organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much
longer. ALI is defined as the Annual Limit of Intake by ingestion which would produce a dose of 20 mSv .
Handling Procedures
1.
2.
3.
4.
Double glove (all direct contact with 59Fe must be avoided).
Finger Badges are to worn if handling quantities in excess of 50 MBq.
Remote handling devices (tongs etc.) should be used when handling mCi amounts.
Use syringe or pipette shields when manipulating stock solutions in excess of 37 MBq.
33
Iodine 125 Data Sheet
Physical Characteristics
Biological Data
Isotope 125I
Half Life 60.28 Days
Mode of Decay Electron Capture
Energy Gamma 0.035 MeV 7%
X-ray 0.027 MeV 128%
Decay Product 125Te
Biological Haft Life 138 Days
Effective Half Life 41.9 Days
Target Organ Thyroid
Shielding Data
Legislative Limits
Exempt Quantity 1 MBq (27 uCi)
ALI Ingestion 1 MBq (27 uCi)
Sewage disposal (University Limit) 100 MBq/yr (2.7
mCi/yr)
Sewage disposal (lab. limit) 0.0037 MBq/L (0.1uCi/L)
Landfill discharge 0.037 MBq/kg (1 uCi/Kg)
Dose Rate from External Exposures
Dose from Skin Contamination
Uniform Deposit 1 kBq/cm2 = 2.1 X 10-2 mSv/hr
0.05 ml droplet 1 kBq = 6.3 X 10-3 mSv/hr
External Dose form a 1 MBq Source in:
Half Value Layer of Lead = 0.03
mm
Contamination
Monitoring Method
Liquid Scintillation
Crystal Scintillation
Geiger Counter
Limits of Contamination
Point source at 30 cm
Skin =0 mSv/hr
Controlled Areas = 300 Bq/cm2
Deep tissue= 3.9 X 10-4 mSv/hr
Uncontrolled Areas = 30 Bq/cm2
10 ml glass vial at 100 cm = 1.4 X10-5 mSv/hr
Contact with a 50 ml glass beaker = 4.1 X10-2 mSv/hr
Contact with 5ml plastic syringe = 0.34 mSv/hr
Notes:
Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an
organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much
longer. ALI is defined as the Annual Limit of Intake by ingestion which would produce a dose of 20 mSv .
Handling Procedures
1. Solutions containing iodine ions should not be made acidic nor stored frozen, both lead to
formation of volatile elemental iodine. As some iodo-compounds can gradually penetrate certain
types of gloves, it is advisable to change gloves often unless it has been determined that the
gloves are impervious to the compound being used. Note however, that the quantity of
radioiodine in normal RIA kits (usually <10 uCi) is such that these can be handled safely with
reasonable care on the open bench.
2. Double gloves and lab coat should be worn when handling 125I .
3. Bioassay are require if 1251 is used as follows:
a. Open Bench greater than 135 uCi (5 MBq)
b. Fume Hood greater than 1.35 mCi (50 MBq)
c. Glove Box(vented) greater than 13.5 mCi (500 MBq)
*Process which involve the generation of volatile iodine must be carried in a fume hood.
4. If a spill occurs the spill should be treated with a solution of excess Sodium Thiosulphate.
5. When possible keep radioiodine solutions above pH 8.0.
6. Vials containing radioiodine should be opened in the fume hood.
7. Avoid direct contact with unshielded containers of radioiodine.
8. Waste radioiodine should be kept in a fume hood or other well ventilated area. (Volatile Iodine
can pass through most plastics)
34
Iodine 131 Data Sheet
Physical Characteristics
Isotope 131I
Half Life 8.06 Days
Mode of Decay Beta & Gamma
Energy Gamma 0.364 MeV Beta Max 0.806 MeV
0.637 MeV Avg. 0.180 MeV
Decay Product 131Xe
Legislative Limits
Biological Data
Biological Half Life 138 Days
Effective Half Life 7.6 Days
Target Organ Thyroid
Shielding Data
Exempt Quantity 0.01 MBq (0.27 uCi)
ALI Ingestion 1 MBq (27uCi)
Sewage discharge (institutional Limit) 10 MBq/yr (270
uCi/yr)
Sewage disposal (laboratory limit) 0.0037 MBq/L(0.1
uCi/L)
Landfill discharge 0.037 MBq/kg (1 uCi/Kg)
Dose Rate from External Exposures
Half Value Layer of Lead = 3mm
Contamination
Monitoring Method
Dose from Skin Contamination
Uniform Deposit 1 kBq/cm2 = 1.6 mSv/hr
0.05 ml droplet 1 kBq = 0.5.7 mSv/hr
Liquid Scintillation
Crystal Scintillation
Geiger Counter
External Dose form a 1 MBq Source in:
Point source at 30 cm
Skin =8.6 X 10-4 mSv/hr
Deep tissue= 3.9 X 10-4 mSv/hr
10 ml glass vial at 100 cm = 6.4 X10-5 mSv/hr
Contact with a 50 ml glass beaker = 0.22 mSv/hr
Contact with 5ml plastic syringe = 1.1 mSv/hr
Limits of Contamination
Controlled Areas = 300 Bq/cm2
Uncontrolled Areas = 30 Bq/cm2
Notes:
Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an
organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much
longer. ALI is defined as the Annual Limit of Intake by ingestion which would produce a dose of 20 mSv .
Handling Procedures
1. Volatilization of iodine is the most significant problem with this isotope. Solutions containing
iodine ions should not be made acidic nor stored frozen, both lead to formation of volatile
elemental iodine. As some iodo-compounds can gradually penetrate certain types of gloves, it is
advisable to change gloves often unless it has been determined that the gloves are impervious
to the compound being used. Note however, that the quantity of radio-iodine in normal RIA kits
(usually <10 uCi) is such that these can be handled safely with reasonable care on the open
bench.
2. Double gloves and lab coat should be worn when handling 131I .
3. Bioassay are require if 1311 is used as follows:
a. Open Bench greater than 135 uCi (5 MBq)
b. Fume Hood greater than 1.35 mCi (50 MBq)
c. Glove Box (vented) greater than 13.5 mCi (500 MBq)
*Process which involve the generation of volatile iodine must be carried in a fume hood.
4. If a spill occurs the spill should be treated with a solution of excess Sodium Thiosulphate.
5. When possible keep radio-iodine solutions above pH 8.0.
6. Vials containing radio-iodine should be opened in the fume hood.
7. Avoid direct contact with unshielded containers of radio-iodine.
8. Waste radio-iodine should be kept in a fume hood or other well ventilated area. (Volatile Iodine
can pass through most plastics)
35
RADIATION CONTAMINATION SURVEY FORM
BUILDING___________ ROOM________________ SURVEY EQUIPMENT ________________________________
Name
Date
AREA
CPM
Bg/cm2
Name
Date
AREA
Bg/cm2
CPM
Name
Date
AREA
1
1
1
2
2
2
3
3
3
4
4
4
5
5
5
6
6
6
7
7
7
8
8
8
9
9
9
10
10
10
11
11
11
12
12
12
Bkg
Bkg
Bkg
Name
Date
AREA
Name
Date
AREA
Name
Date
AREA
CPM
Bg/cm2
Bg/cm2
CPM
1
1
1
2
2
2
3
3
3
4
4
4
5
5
5
6
6
6
7
7
7
8
8
8
9
9
9
10
10
10
11
11
11
12
12
12
Bkg
Bkg
Bkg
36
CPM
Bg/cm2
CPM
Bg/cm2
UNIVERSITY of WATERLOO RADIOISOTOPE INVENTORY
Location
Isotope:___________ Date Received(D/M/Y)__________
Room: _________
Material: _________________ Lot #: _______________
Supervisor: __________________
Activity (mCi): ___________
Vial Id:_____________
Permit #: ______
Volume (μL): __________
DATE USED
User
Initials
Contamination
Monitoring
Amount Used (μL)
Date
Type of Waste
Type
of
Waste
Waste
Stream
% of material in
each waste
stream
Waste Stream
L= Aqueous
O= Organic
S=Solid
A= Animal Carcass
1=Municipal Garbage
2= Municipal Sewer
3=U W Environmental Safety Facility
4= Other (specify)
Package Contamination_______________ Signature_________________ PO No.________
37