DEN - Saclay – Nuclear Material departemen "Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 1 DMN / SRMA Tensile properties and Tensile properties and microstructure of austenitic microstructure of austenitic steels irradiated in different steels irradiated in different reactors reactors Ph. Dubuisson X. Averty M. Žamboch V.K. Shamardin V.I. Prokhorov J.P. Massoud C. Pokor Influence of Atomic Displacement Influence of Atomic Displacement Rate on Rate on Radiation-induced Aging of Power Radiation-induced Aging of Power Reactor Reactor Ulianovsk, Russia - October 2 - 8, Ulianovsk, Russia - October 2 - 8, Y. Bréchet
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Tensile properties and microstructure of austenitic steels irradiated in different reactors
Tensile properties and microstructure of austenitic steels irradiated in different reactors. Ph. Dubuisson X. Averty. V.K. Shamardin V.I. Prokhorov. J.P. Massoud C. Pokor. M. Žamboch. Y. Bréchet. Influence of Atomic Displacement Rate on Radiation-induced Aging of Power Reactor - PowerPoint PPT Presentation
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DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 1
DMN / SRMA
Tensile properties and microstructure Tensile properties and microstructure of austenitic steels irradiated in of austenitic steels irradiated in
different reactorsdifferent reactors
Ph. DubuissonX. Averty
M. Žamboch
V.K. ShamardinV.I. Prokhorov
J.P. MassoudC. Pokor
Influence of Atomic Displacement Rate onInfluence of Atomic Displacement Rate onRadiation-induced Aging of Power ReactorRadiation-induced Aging of Power Reactor
Ulianovsk, Russia - October 2 - 8, 2005Ulianovsk, Russia - October 2 - 8, 2005
Y. Bréchet
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 2
DMN / SRMA
Reach "rapidly" the end-of-life doses FBRFBR• Mechanical properties
• SCC
• Microstructure
• Modelling
Objective Objective : Evaluate the effects of neutron irradiation on mechanical properties and resistance to SCC
Irradiations in Experimental Reactors
Temperature
370°C
300°C
320°C Bor-60 BORISBORIS
EBR-II/Phénix
30 dpa
Dose
PWR40 years
95 dpa
360°C
Materials Representative of Core Internals of the PWRs
SA 304L Baffle plates, Former, Core barrel
CW 316 Baffle bolts
C Cr Ni Mn Mo Si Cu
SA 304L 0.022 18.6 9.9 1.8 0.06 0.36 0.25
CW 316 0.054 16.6 10.6 1.1 2.25 0.68 0.24
Tensile specimens
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 3
DMN / SRMA
Irradiations in Experimental Reactors
Irradiations in FBR Irradiations in FBR Spectrum effect ? Spectrum effect ?
He effect• Mechanical properties
• SCC tests
BOR-60 / Osiris Tensile 10 dpa
1.E+10
1.E+11
1.E+12
1.E+13
1.E+14
1.E+15
1.E-04 1.E-01 1.E+02 1.E+05 1.E+08Energie en eV
E.F(E).Flux
(cm-2s-1)
PWROsirisSMBOR-60
Area without shieldFast & thermal Fast & thermal
neutronsneutrons
2 irradiation areas
Tensile
Area with Hf shieldFast neutronsFast neutrons
Steel
Temperature
370°C
300°C
320°C Bor-60 BORISBORIS
EBR-II/Phénix
30 dpa
Dose
PWR40 years
95 dpa
360°C
SM
Osiris
Flux, GazFlux, Gaz He, H He, H
Modelling
SAMARASAMARA
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 4
DMN / SRMA
0
5
10
15
20
25
30
35
40
0 20 40 60 80 100 120 140
Dose (dpa)
U.E. (%)
0
1
0 20 60 100 140
Tensile propertiesFast Breeder Reactor BOR 60
Te = 330°C3 10-4 s-1
320°C
BOR 60BOR 60
0
200
400
600
800
1000
1200
0 20 40 60 80 100 120 140
Dose (dpa)
YS (MPa)0.2%
SA 304L
CW 316
SA 304L
CW 316
Saturation
Total Elongation5 – 10%
U.T.S. YS0.2%
CW 316 > SA 304L - 125 dpa
SA 304L > 5 dpaCW 316 10 dpa
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 5
DMN / SRMA
0
200
400
600
800
0 2 4 6 8 10 12
Elongation (%)
Stress (MPa)
BOR 60BOR 60
0
200
400
600
800
0 2 4 6 8 10 12
Elongation (%)
Stress (MPa)
Tensile propertiesBOR 60 - Osiris
Osiris
0
200
400
600
800
0 2 4 6 8 10 12
Elongation (%)
Stress (MPa)
5 dpa5 dpa
0
200
400
600
800
0 2 4 6 8 10 12
Elongation (%)
Stress (MPa)
Osiris
10 dpa10 dpa
No difference between Osiris and BOR 60 No effect of neutron spectrum
Saturation of mechanical properties > 5 dpa
Te = 330°C3 10-4 s-1
SA 304LSA 304L
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 6
DMN / SRMA
0
5
10
15
20
25
30
35
40
0 10 20 30
Dose (dpa)
U.E. (%)
0
200
400
600
800
1000
1200
0 10 20 30
Dose (dpa)
YS (MPa)0.2%
Tensile propertiesBOR 60 - Osiris
BOR 60BOR 60 SA 304L
CW 316
SA 304L
CW 316
OsirisOsiris
No difference between Osiris and BOR 60 No effect of neutron spectrum
Saturation of mechanical properties SA 304LSA 304L 5 dpa5 dpaCW 316CW 316 10 dpa10 dpa
Te = 330°C3 10-4 s-1
0
200
400
600
800
1000
1200
0 10 20 30
Dose (dpa)
YS (MPa)0.2%
0
5
10
15
20
25
30
35
40
0 10 20 30
Dose (dpa)
U.E. (%)
0
1
0 10 20 300
1
0 10 20 30
320°C
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 7
DMN / SRMA
0
200
400
600
800
0 2 4 6 8 10
Elongation (%)
Stress (MPa)
Tensile propertiesHelium effect SM 2
0
200
400
600
800
0 2 4 6 8 10
Elongation (%)
Stress (MPa)
SM 2SM 2
6 dpa6 dpa 17 dpa17 dpaSame FluxSame Flux
10 appm10 appmHeHe
300 appm300 appmHeHe
No obvious effect of Helium (H2) contentSaturation of mechanical properties < 6 dpa
Te = 330°C3 10-4 s-1
300°C
14 appm14 appmHeHe
600 appm600 appmHeHe
SA 304LSA 304L
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 8
DMN / SRMA
0
5
10
15
20
25
30
35
40
0 10 20 30
Dose (dpa)
U.E. (%)
0
5
10
15
20
25
30
35
40
0 10 20 30
Dose (dpa)
U.E. (%)
0
5
10
15
20
25
30
35
40
0 10 20 30
Dose (dpa)
U.E. (%)
0
200
400
600
800
1000
1200
0 10 20 30
Dose (dpa)
YS (MPa)0.2%
0
200
400
600
800
1000
1200
0 10 20 30
Dose (dpa)
YS (MPa)0.2%
Tensile propertiesBOR 60 – Osiris – SM 2
BOR 60BOR 60SA 304L
CW 316
SA 304L
CW 316
OsirisOsiris
Te = 330°C3 10-4 s-1
No obvious effect of helium (H2) on tensile characteristics
Tensile characteristics similar to those measured after irradiationin Bor-60 (FBR) at 320°C both for CW 316 and SA 304L
0
200
400
600
800
1000
1200
0 10 20 30
Dose (dpa)
YS (MPa)0.2%
0
1
0 10 20 300
1
0 10 20 300
1
0 10 20 30SM 2SM 2
No flux effect
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 9
DMN / SRMA
Tensile properties
Saturation dose at 5 dpa for SA 304L10 dpa for CW 316
No evolution between 10 and 125 dpa for both SA 304L - CW 316
CW 316 > SA 304L hardness – residual ductility
No neutron spectrum effect on tensile charactericticsGaz content and flux
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 10
DMN / SRMA
Hardening Model
Evolution of the Yield Stress after irradiationTemperature, fluence, neutron spectrum
Model of the population of point defects clusters
(dislocation loops)
Model of hardeningby a cluster population
proportional , L
Microstructural data ofneutron irradiated materials
TEM
Yield Strength of neutron irradiated materials
Tensile tests
PWR InternalsPWR InternalsEBR II, Osiris, BOR 60
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 11
DMN / SRMA
Microstructure
Frank Loops
No precipitationNo more dislocation lines
Saturation for dose about 5 - 10 dpasize SA 304L 316density SA 304L > CW 316
0
10
20
0 10 20 30 40 50
dose dpa
diameternm
1.E+22
1.E+23
1.E+24
0 10 20 30 40 50
dose dpa
density
m-3
375°C
330°C
375°C
330°C
SA 304L
Main featureFrank loops formation
Black dots
Voids
SA 304L CW 316
EBR II375°C - 10 dpa
EBR IIOsiris
BOR 60
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 12
DMN / SRMA
Microstructure ModellingFrank loop
Chemical kinetic Model"Cluster Dynamics"
Dislocation network evolution
Loops
dt
dC iv,
Evolution of the concentration of point defects
Production - Recombination (v-i) - Loss of v and i at sinks- Agglomeration
Evolution of the concentration of interstitial or vacancy cluster containing n defects
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 13
DMN / SRMA
Microstructure ModellingFrank loop
Chemical kinetic Model"Cluster Dynamics"
External source of irradiation
defects
Interstitial or .
vacancy
Interstitial vacancycluster
Interstitial or vacancy
sinks : clusters dislocations grain boundaries /
free surfaces
Neutrons
Homogeneous medium
1020
1021
1022
1023
0
10
20
30
40
50
0 20 40 60
Dosedpa
Densitym-3
Diameternm
0
5 1020
1 1021
1,5 1021
2 1021
2,5 1021
0 5 10 15 20 25
Density
Diameternm
m-3
0,1 dpa
1 dpa
10 dpa
30 dpa50 dpa
Loops
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 14
DMN / SRMA
Microstructure ModellingFrank loops
1. Adjust material parameters of the model on low dose data EBR II - Osiris2. Predict the behavior at higher doses EBR II – Osiris –
BOR 603. Comparison with experimental data – BOR 604. Comparison with future results high doses BOR 60 (90 dpa) and Osiris (10 dpa)
Chemical kinetic Model"Cluster Dynamic"
0
10
20
30
0 10 20 30 40 50
0
10
20
30
0 10 20 30 40 50
0
10
20
30
0 10 20 30 40 501,E+20
1,E+21
1,E+22
1,E+23
1,E+24
0 10 20 30 40 50
dose dpa
density
m-3
1,E+20
1,E+21
1,E+22
1,E+23
1,E+24
0 10 20 30 40 50
1,E+20
1,E+21
1,E+22
1,E+23
1,E+24
0 10 20 30 40 50
1,E+20
1,E+21
1,E+22
1,E+23
1,E+24
0 10 20 30 40 50
0
10
20
30
0 10 20 30 40 50
dose dpa
diameternm SA 304LSA 304L
375°C
330°C
Emv 1.35
eV
Emi 0.45
eV
Eb2i 0.6
eV
0 1010 cm-2
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 15
DMN / SRMA
Experimental Simulation Material
Temperature (°C)
dose (dpa) i (nm) i (m
-3) v (nm) v (m-3) i (nm) i (m
-3)
320 10 11,5 25 10 21 / / 11,2 27 10 21
CW 316 320 19 7 92 10 21 2 < 10 20 12,8 32 10 21
333 24 10 12 10 21 / / 18,7 18 10 21
SA 304 310 35 10 15 10 21 1 1 10 21 10,2 80 10 21
In terms of interstitial loops size and density,the results of the model are in relatively good agreementwith the results obtained from field experience in PWRs.
Microstructure of expertised components
In agreement with results from experimental reactors
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 16
DMN / SRMA
Hardening - Orowan Model
Dislocations networkevolution
Good agreement at low dose
Data / Model
Cluster DynamicsModel
Model of defect clusters no diameter and density saturationOrowan hardening no hardening saturation
loops 0,4
loopsloopsloopsb M + l ( ) -di
do
- -di
do
-
?
Same for CW 316
SA 304L
330°C
0
400
800
1200
0 20 40 60 80 100
dose dpa
Mpa
Osiris
BOR 60
0
400
800
1200
0 20 40 60 80 100
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 17
DMN / SRMA
Hardening due to Frank Loops
Defaulting of the Frank loops Transformation in perfect loop under a applied stress
Critical shear stress for defaulting a Frank loop of diameter One relation between and
and increase with dose Perfect loop glide and annihilate Saturation at the critical stress
Critical dose for the mechanism of hardening
Modified Orowan Model
dcMain parameters : Stacking Fault Energy, d
One adjustable parameterNumber of dislocations in the pile-up
loopsloopsloopsb M
loopsloopsloopsb M
No Defaulting
Defaulting
No Defaulting
Defaulting
dose
DefaultingNo
Defaulting
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 18
DMN / SRMA
Modified "Orowan" model Hardening model permitting defaulting of Frank Loops
Saturation of Hardening
Well description of experimental data by the model
330°C Good description of experimental data375°C Need data at high dose to verify Voids data / Model in SA 304
2 steels : 0
Voids
0 1010 cm-2
26 Jm-2
0 1014 cm-2
42 Jm-2
0
200
400
600
800
0 20 40 60 80 100
dose dpa
MPa
330°C
375°C
CW 316CW 316
330°C
375°C
0
200
400
600
800
0 20 40 60 80 100
dose dpa
MPa 330°C
375°C
SA 304L
330°C
375°C
SA 304L
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 19
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 21
DMN / SRMA
Conclusions - Perspectives Tensile properties
Saturation dose at 5 dpa for SA 304L10 dpa for CW 316
CW 316 > SA 304L hardness – residual ductility No neutron spectrum effect on tensile characterictics
Gaz content and flux
Microstructure High density of small Frank loops + Voids at high temperature in SA 304L Disappearance of the initial dislocations network No precipitation Reproduce Microstructure observed on PWR components
Hardening Model Cluster Dynamic Model
Good agreement with TEM quantification – Frank loopsNo real saturation of loop number density
and diameter Hardening Model
● Orowan Model No saturation of hardening● Modified Orowan Model permitting the defaulting of Frank loops
Saturation of Hardening
No evolution between10 and 125 dpa
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 22
DMN / SRMA
Conclusions - Perspectives
In simulated PWR water Total Elongation of the SSRT specimens strongly reduced Fracture surface partly intergranular T.E. lower - Fracture surfaces more intergranular “low helium” content
Further examinations and SCC tests will be performed on more highly irradiated materials
Mechanical properties saturate He content increases
Intergranular fracture SM 2 > BOR 60Flux effect ? Medium ?Flux effect ? Medium ?
DEN - Saclay – Nuclear Material departement
"Influence of atomic displacement rate… " Workshop - Ulyanovsk - October 5, 2005 Ph. Dubuisson - 23
DMN / SRMA
This work was performed through a collaboration betweenEDF, CEA and RIAR partly sponsored by EPRI