BA IIFERC Prroject
DEMO
O R&D Acctivities
R
R&D ON MATERI
M
IALS ENG
GINEERIING FOR
R DEMO BLANKE
ET
(EU-T3)
Annuaal Reporrt 2010
of
Progrress repoort of irrradiation
n experiiment on
n small siize speciimens
in high flux testt modulee
(Taask T3-2
2-3)
Respo
onsible Officcer: Susanaa Clement Lorenzo
Technical Responsiblle Officer: Mageshwara
M
an Ramesh
Structurral Material Analysis
Nucllear Materiaals Sciencess (NMS) Insstitute
Belgiaan Nuclear R
Research Center (SCK
K•CEN)
Bo
oeretang 2000, B-2400 Mol,
M Belgiu
um
Author((s)
Reviewer(s)
Name
Mageshwaran Ramessh
Nadine Baaluc
Susana Cllement Loreenzo
Affiliation
A
SCK●CEN,T
S
Technical R
Responsible Officer
CRPP,
C
Techn
nical Coorddinator
Fusion
F
for Energy,
E
Respponsible Offficer
SCIEENTIFIC REPORT
SCK
K•CEN-BLG
G -1076
Progreess report
r
on irradiation
n
experim
ment on
o sma
all size specim
mens in
n
the higgh flux test module
m
M. Ramessh, P. Jacq
quet and R.
R Chaouaddi
PROGRE
ESS REPO
ORT
Contracct No: CO-90-10
0-2655-000
February 2011
NMS
N
EN
SCK•CE
Boeretangg 200
2400 Moll
Belgium
Distribution list
Name
Institute
Number
M.Ramesh
R. Chaouadi
V. Massaut
P. Jacquet
SMA- SCK.CEN
SMA - SCK.CEN
HWP - SCK.CEN
TCH - SCK.CEN
1
1
1
1
A. Moesland
F. Arbeiter
N. Scheel
H. Tanigawa
E. Wakai
T.Yamanishi
J. Molla
N. Baluc
M. Araki
K. Hayashi
S. Clement Lorenzo
R. Heidinger
KIT
KIT
KIT
JAEA
JAEA
JAEA
JAEA
CRPP
IFERC-PT
IFERC-PT
F4E
F4E
1
1
1
1
1
1
1
1
1
1
1
1
Secretariaat NMS
3
TOTAL COPIES
19
.Verified by:
,
.• Approved
'
.': '."
Patrice Jacquet
Ir/02/~II
~
by:
Rachid Chaouadi
RESTRICTED
All property rights and copyright are reserved. Any communication or reproduction of this document, and any
communication or use of its content without explicit authorization is prohibited. Any infringement to this rule is
. illegal and entitles to claim damages from the infringer, without prejudice to any other right in case of granting a
patent or registration in the field of intellectual property. SCK·CEN, Boeretang 200, 2400 Mol, Belgium.
SCIENTIFIC REPORT
SCK•CEN-BLG-1076
Progress report of irradiation
experiment on small size specimens in
the high flux test module
M. Ramesh, P. Jacquet and R. Chaouadi
Contract No: CO-90-10-2655-00
February, 2011
Status: Unclassified
NMS
SCK•CEN
Boeretang 200
2400 Mol
Belgium
R-5146 – Page 5 of 15
Table of contents
1 Introduction ........................................................................................................................... 1 2 Description of Irradiation load ............................................................................................ 2 2.1 Material and test matrix...................................................................................................... 2 2.2 Specimen procurement ........................................................................................................ 4 2.3 Specimen fabrication .......................................................................................................... 4 2.4 Specimen localization in HFTM capsule ............................................................................ 5 2.5 Description of irradiation conditions. ................................................................................ 7 3 Finite element calculations. .................................................................................................. 7 Acknowledgements ....................................................................................................................... 9 References ...................................................................................................................................... 9 IFERC-R-T4-10-JA
1
Introduction
This report describes the progress made in the IFREC/DEMO R&D program during the
year 2010 at SCK●CEN.
The main project objectives are twofold:
1. Demonstrating the possibility to irradiate small specimens in the HFTM modules
that will be used in IFMIF [1].
2. Performing detailed study with the support of finite element calculations and
analytical work to validate the specimen geometry and size to reliably characterize
the mechanical properties of unirradiated and in future of irradiated materials [1].
In order to achieve the first part of the above objectives, the preparatory phase (material
procurement, specimen fabrication and preparation of irradiation rig) have started, mainly
aimed to performing the irradiation on small size samples in high flux test modules. The
irradiation exercise will be performed on three different materials, EUROFER-97 and F82H
RAFM steels and a 14%Cr-ODS material at 250 and 550 ºC. This programme encompasses
different specimens to evaluate the effect of irradiation on hardening, fracture toughness and
creep properties. This report gives detailed information on the specimens to be loaded into the
High Flux Test Module (HFTM) capsules that will be irradiated in the BR2 reactor [2]. Three
HFTM capsules will be irradiated together in the same irradiation device called "LIBIDO".
The first capsule will be irradiated at 250°C, the second one at 550°C and the third one at a
temperature fluctuating between 250 and 550°C. Given the time schedule of the irradiation, it
was not possible to first optimize the specimen size in the unirradiated condition and then
perform irradiation using these "optimized" specimens. Therefore, based on previous
experience, we selected specimen geometries to be irradiated while performing in parallel
detailed study on specimen optimization. As a matter of fact, it is anticipated that the selected
geometries will be very close to optimum and therefore this work will be relevant to SSRT
studies that are critical for the future use of IFMIF.
For the second objective which deals with the effect of specimen size on mechanical
properties, finite element calculations to determine the effect of specimen geometry on fracture
properties has been started.
IFERC-R-T4-10-JA
2
2.1
Description of Irradiation load
Material and test matrix
In the current irradiation program, the focus is on three different Reduced Activity
Ferritic Martensitic (RAFM) steels: Eurofer-97 (E97), F82H and Oxide Dispersion
Strengthened (ODS) steels.
To determine the neutron irradiation effects on these materials, we will use the following
specimen geometries:

flat versus cylindrical tensile geometry for the flow properties;

mini–CT (Compact Tension) specimens for fracture toughness measurement in
the transition regime (master curve);

small–CT specimens for crack resistance (JR-curve) measurement;

flat plate for microstructure examination;

bend plate for irradiation creep measurement.
Table 1 summarizes the specimens that will be loaded in the two HFTM capsules for
irradiation at constant temperatures (250°C and 550°C). Although different from the IFMIF
current reference loading [KIT drawing ref FZK-00025180], this specimen loading scheme is
appropriate for material characterization.
2
IFERC-R-T4-10-JA
Table 1. Summary of the test matrix.
Type
Small
CT
Drawing #
100862-010
Material
Irradiation temperature
E97
n.a.
20 - 250 - 550
0
3
250
250
0.3 - 0.4
1
550
550
0.4 - 0.5
1
n.a.
20 - 250 - 550
0
3
250
250
0.3 - 0.4
1
550
550
0.4 - 0.5
1
n.a.
20 - 250 - 550
0
3
n.a.
n.a.
0.3 - 0.4
0
550
550
0.4 - 0.5
4
F82H
ODS
E97
Mini CT
100862-011
F82H
ODS
E97
Tensile
(cyl.)
100862-012
F82H
ODS
E97
Tensile
(flat)
100862-013
F82H
ODS
E97
Plate
(MS)
100862-014
F82H
ODS
E97
Bend
Plate
100862-015
F82H
ODS
Test temperature [°C]
Target Dose Range
Nbr of specimens
per T°
n.a.
temp. range
0
15
250
temp. range
0.3 - 0.4
15
550
n.a.
0.4 - 0.5
0
n.a.
temp. range
0
15
250
temp. range
0.3 - 0.4
15
550
n.a.
0.4 - 0.5
0
n.a.
temp. range
0
10
n.a.
n.a.
0.3 - 0.4
0
n.a.
n.a.
0.4 - 0.5
0
n.a.
20 - 250 - 550
0
6
250
250
0.3 - 0.4
4
550
550
0.4 - 0.5
3
n.a.
20 - 250 - 550
0
6
250
250
0.3 - 0.4
4
550
550
0.4 - 0.5
3
n.a.
temp. range
0
6
n.a.
n.a.
0.3 - 0.4
0
550
550
0.4 - 0.5
4
n.a.
20 - 250 - 550
0
6
250
250
0.3 - 0.4
18
550
550
0.4 - 0.5
24
n.a.
20 - 250 - 550
0
6
250
250
0.3 - 0.4
18
550
550
0.4 - 0.5
24
n.a.
temp. range
0
6
n.a.
n.a.
0.3 - 0.4
0
550
550
0.4 - 0.5
12
4
n.a.
n.a.
0
250
n.a.
0.3 - 0.4
5
550
n.a.
0.4 - 0.5
13
4
n.a.
n.a.
0
250
n.a.
0.3 - 0.4
5
550
n.a.
0.4 - 0.5
13
n.a.
n.a.
0
4
n.a.
n.a.
0.3 - 0.4
0
550
n.a.
0.4 - 0.5
14
n.a.
n.a.
0
0
250
250
0.3 - 0.4
4
550
550
0.4 - 0.5
4
n.a.
n.a.
0
0
250
250
0.3 - 0.4
4
550
550
0.4 - 0.5
4
n.a.
n.a.
0
0
n.a.
n.a.
0.3 - 0.4
0
550
550
0.4 - 0.5
8
3
Total
5
5
7
30
30
10
13
13
10
Identification
E31 → E33
E34
E35
F31 → F33
F34
F35
O11 →
/
O14 →
E1 → E15
E16 → E30
/
F1 → F15
F16 → F30
/
O1 → O10
/
/
E1 → E6
E1 → E4
E1 → E3
F1 → F6
F1 → F4
F1 → F3
O1 → O6
/
O1 → O4
48
E
48
F
18
O
22
E
22
F
18
O
8
E1 → E8
8
F1 → F8
8
O1 → O8
IFERC-R-T4-10-JA
2.2
Specimen procurement
Eurofer 97 material is supplied by KIT, while F82H plates were supplied by CRPP. The
ODS material is provided by SCK•CEN. At this stage, we are considering a 14%Cr ferritic
ODS steel with the following chemical composition (Table 2).
Table 2. Chemical composition of the all three materials (in wt.%).
Fe
C
Cr
W
Ti
Y
Si
Ni
Mn
V
1
0.4
0.25
0.3
0.16
0.3
-
1.94 0.01
-
0.11
0.02
0.16 0.16
1.1
-
0.05 0.005
14% Cr ODS
steel
balance 0.052
14
F82H
balance 0.09
7.7
Eurofer 97
balance 0.11
9
0.01
0.4
0.16
Characterization of this ODS steel is in progress (tensile properties, microstructure and
fracture toughness). The microstructure and mechanical properties of the un-irradiated
Eurofer-97 and F82H materials will be performed soon.
2.3
Specimen fabrication
The specimens are already manufactured according to the SCK•CEN drawings referred
in Table 1 (see also the drawings in annex 1).
Important remarks:
a) Each specimen should be dimensionally controlled and reported after manufacturing
b) The Compact Tension (CT) specimens (small and mini) will be manufactured
according to the following steps:

the specimen is machined according to the drawing except its front and rear
surfaces;

the specimen is controlled: dimensions and defects at surface;

the specimen is fatigue precracked up to a crack length–to–width ratio of
~0.5;

the specimen is 20% side-grooved and finally controlled.
Our proposal for the specimen manufacturing process is the following:
4
IFERC-R-T4-10-JA
a) Eurofer97 specimens will be manufactured by KIT (CT: only first step).
b) ODS and F82H specimens will be manufactured by SCK•CEN.
c) All the specimens will be controlled at SCK•CEN.
d) Fatigue precracking of all CT specimens will be performed at SCK•CEN.
Final machining, namely side-grooving, of all CT specimens will be performed at
SCK•CEN.
2.4
Specimen localization in HFTM capsule
The final specimens' location in the HFTM capsule is not yet definitively decided but we
have defined both capsules loading that include all the specimens listed in Table 1.
The 3D illustrations below (Figures 4 and 5) show the capsules' loading from 2 sides.
Figure 4. HFTM Capsule loading to be irradiated at 250°C: (a) top view; (b) bottom
view.
5
IFERC-R-T4-10-JA
Figure 5. HFTM Capsule loading to be irradiated at 550°C : (a) top view; (b) bottom
view.
6
IFERC-R-T4-10-JA
2.5
Description of irradiation conditions.
Three HFTM capsules will be irradiated together in the same irradiation device called
"LIBIDO". The first capsule will be irradiated at 250°C and the second one at 550°C. Both
capsules will receive dose between ~0.3 and ~0.6 dpa, respectively. We are foreseeing the
irradiation campaign of the above task on the last reactor cycle of 2011 (December) in the BR2
reactor at SCK•CEN. For the required neutron dose, the samples have to be irradiated in the rig
for approximately one year.
3
Finite element calculations.
While extensive preparatory work was made for starting the irradiation campaign, in
parallel considerable efforts were made, primarily aiming at understanding the effects of size
on fracture behavior in both ductile and brittle regimes.
In this regard, compact tensions specimens of four different sizes (1T, 0.5T, 0.25T and
0.16T) were modeled in ANSYS work bench (Fig. 6). The 3D finite element model was made
with the refined element size of 0.18 μm close to the crack tip (Fig. 7) in order to more closely
evaluate the plastic zone evolution and stress-strain distribution ahead of the crack tip. In order
to have a fair comparison of the effect of size on the stress distribution near the crack tip the
element size is maintained constant near the crack regardless of the specimen geometry. It can
be noticed from the figures 6 and 7 that the finite element model was made only for one fourth
of the sample geometry due to inherent symmetry conditions of this geometry, this in turn can
also help in reducing the computation time.
7
IFERC-R-T4-10-JA
Figure 6. The different sized of compact tensions specimens which be investigated for
the effect of size on their fracture properties (a) Geometry; (b) Finite element model.
8
IFERC-R-T4-10-JA
Figure 7. The refined elements near the crack tip to evaluate the stress gradient and its
distribution.
The material data for the finite element model is awaited since this will be inputted from
the tensile properties of the un-irradiated materials. After establishing material properties at
upper and lower shelf temperatures from the tensile tests, the fracture properties will be
investigated and compared between the experiment and simulation.
ACKNOWLEDGEMENTS
The Authors gratefully acknowledge the personnel of LHMA, BR2 and TCH departments
who collaborated to the setting up of this irradiation campaign.
REFERENCES
[1] R. Chaouadi et al., R & D on Materials Engineering for DEMO blanket - SCK●CEN
contribution: “7th Workshop on DEMO R&D in BA ”International Symposium”,
Barcelona, 4-6/10/2010.
[2] P. Jacquet, SCK●CEN Technical note, IFMIF – EVEDA – Broader approach HFTM
capsules irradiation in BR2: Specimens loading characteristics-Rev 1 (2010).
9
IFERC-R-T4-10-JA
ANNEXURE 1
10
8
7
6
5
4
3
2
1
FZK capsule bottom part.
Micro-structure specimen holder
see dwg. SCK/CEN n 100862-021 - item 2,
with micro-structure specimen (10x)
see dwg. SCK/CEN n 100862-014.
Mini CT-specimen (30x)
see dwg. SCK/CEN n 100862-011.
Flat tensile specimen holder - type 1
see dwg. SCK/CEN n 100862-021 - item 1.
F
F
Flat tensile specimen (12x)
see dwg. SCK/CEN n 100862-013.
Flat tensile specimen (12x)
see dwg. SCK/CEN n 100862-013.
2 specimen bending block assemblies (SBB).
for bending block specimen see dwg. SCK/CEN n 100862-015.
and for specimen bending block parts see
dwg. SCK/CEN n 100862-016.
E
E
2 small CT-specimen
see dwg. SCK/CEN n 100862-010
D
Flat tensile specimen holder - type 1
see dwg. SCK/CEN n 100862-021 - item 1.
Round tensile specimen (2x)
see dwg. n SCK/CEN n 100862-012
D
Round tensile specimen (6x)
see dwg. n SCK/CEN n 100862-012
Flat tensile specimen (12x)
see dwg. SCK/CEN n 100862-013.
C
C
Flat tensile specimen holder - type 2
see dwg. SCK/CEN n 100862-021 - item 5.
Round tensile specimen holder-type 1
see dwg.SCK/CEN n 100862-021 - item 3.
Round tensile specimen holder-type 2
see dwg.SCK/CEN n 100862-021 - item 4.
B
Assembly:
Drawn by: Valenberghs J Dat.: 2010-10-29
Checked:
Dat.:
Verified:
Dat.:
Approved:
Dat.:
Rev.
Nr.:
Inst.:
Exp. Grp.: ANS / DEO
Date:
Modification
Rev.:
100862-020
FZK-capsule 250 C
CC / WBS:
A
This drawing is the exclusive property of the SCK-CEN.
Reproduction or disclosure to third parties, in any form whatsoever,
are not allowed unless written consent of the proprietor.
8
7
6
5
SCK CEN
STUDIECENTRUM VOOR KERNENERGIE
CENTRE D'ETUDE DE L'ENERGIE NUCLEAIRE
4
B
Bill of materials:
CFC
Dossier:
BFBROADAPP-013010
Par.:
Status:
LIBIDO
Roughness
Surface:Ra[ m]
Units:
Scale:
mm
Tolerance:
A
LIBIDO
SPECIMEN LAYOUT OF 250 C CAPSULE
3
2
1
8
7
6
5
4
3
2
1
FZK capsule bottom part.
Micro-structure specimen holder - type 1
see dwg. SCK/CEN n 100862-023 - item 4,
with micro-structure specimen (14x)
see dwg. SCK/CEN n 100862-014.
Round tensile specimen (4x)
see dwg. SCK/CEN n 100862-012
Micro-structure specimen holder - type 2
see dwg. SCK/CEN n 100862-023 - item 5,
with micro-structure specimen (26x)
see dwg. SCK/CEN n 100862-014.
Round tensile specimen (6x)
see dwg. SCK/CEN n 100862-012
F
F
Flat tensile specimen holder - type 1
see dwg. SCK/CEN n 100862-023 - item 1.
Round tensile specimen holder (2x)
see dwg. SCK/CEN n 100862-023 - item 2.
Flat tensile specimen (12x)
see dwg. SCK/CEN n 100862-013
4 specimen bending block assemblies (SBB).
for bending block specimen see dwg. SCK/CEN n 100862-015.
and for specimen bending block parts see
dwg. SCK/CEN n 100862-016.
Flat tensile specimen (18x)
see dwg. SCK/CEN n 100862-013
E
E
Round tensile specimen holder (3x)
see dwg. SCK/CEN n 100862-023 - item 2.
Flat tensile specimen (18x)
see dwg. SCK/CEN n 100862-013
Flat tensile specimen holder - type 1
see dwg. SCK/CEN n 100862-023 - item 1.
D
Flat tensile specimen holder - type 2
see dwg. SCK/CEN n 100862-023 - item 3.
D
Flat tensile specimen (12x)
see dwg. SCK/CEN n 100862-013
3 small CT-specimen
see dwg. SCK/CEN n 100862-010
Flat tensile specimen holder - type 2
see dwg. SCK/CEN n 100862-023 - item 3.
C
C
3 small CT-specimen
see dwg. SCK/CEN n 100862-010
B
Assembly:
Drawn by: Valenberghs J Dat.: 2010-11-02
Checked:
Dat.:
Verified:
Dat.:
Approved:
Dat.:
Rev.
Nr.:
Inst.:
Exp. Grp.: ANS / DEO
FZK-capsule 550 C
Date:
Modification
Rev.:
100862-022
CC / WBS:
A
This drawing is the exclusive property of the SCK-CEN.
Reproduction or disclosure to third parties, in any form whatsoever,
are not allowed unless written consent of the proprietor.
8
7
6
5
SCK CEN
STUDIECENTRUM VOOR KERNENERGIE
CENTRE D'ETUDE DE L'ENERGIE NUCLEAIRE
4
B
Bill of materials:
Units:
Scale:
mm
Dossier:
BFBROADAP-013010
Par.:
Status:
LIBIDO
Roughness
Surface:Ra[ m]
Tolerance:
A
LIBIDO
SPECIMEN LAYOUT OF 550 C CAPSULE
3
2
1