TY - JOUR
T1 - Behavior of ferritic/martensitic steels after n-irradiation at 200 and 300 °C
AU - Matijasevic, Milena
AU - Lucon, Enrico
AU - Al Mazouzi, Abderrahim
A2 - Aït Abderrahim, Hamid
A2 - De Bruyn, Didier
A2 - Van Dyck, Steven
N1 - Score = 10
PY - 2008/6/30
Y1 - 2008/6/30
N2 - High chromium ferritic/martensitic (F/M) steels are considered as the most promising structural materials
for accelerator driven systems (ADS). One drawback that needs to be quantified is the significant hardening
and embrittlement caused by neutron irradiation at low temperatures with production of
spallation elements. In this paper irradiation effects on the mechanical properties of F/M steels have been
studied and comparisons are provided between two ferritic/martensitic steels, namely T91 and EUROFER97.
Both materials have been irradiated in the BR2 reactor of SCK-CEN/Mol at 300 C up to doses ranging
from 0.06 to 1.5 dpa. Tensile tests results obtained between 160 C and 300 C clearly show
irradiation hardening (increase of yield and ultimate tensile strengths), as well as reduction of uniform
and total elongation. Irradiation effects for EUROFER97 starting from 0.6 dpa are more pronounced compared
to T91, showing a significant decrease in work hardening. The results are compared to our latest
data that were obtained within a previous program (SPIRE), where T91 had also been irradiated in BR2
at 200 C (up to 2.6 dpa), and tested between 170 C and 300 C. Irradiation effects at lower irradiation
temperatures are more significant.
AB - High chromium ferritic/martensitic (F/M) steels are considered as the most promising structural materials
for accelerator driven systems (ADS). One drawback that needs to be quantified is the significant hardening
and embrittlement caused by neutron irradiation at low temperatures with production of
spallation elements. In this paper irradiation effects on the mechanical properties of F/M steels have been
studied and comparisons are provided between two ferritic/martensitic steels, namely T91 and EUROFER97.
Both materials have been irradiated in the BR2 reactor of SCK-CEN/Mol at 300 C up to doses ranging
from 0.06 to 1.5 dpa. Tensile tests results obtained between 160 C and 300 C clearly show
irradiation hardening (increase of yield and ultimate tensile strengths), as well as reduction of uniform
and total elongation. Irradiation effects for EUROFER97 starting from 0.6 dpa are more pronounced compared
to T91, showing a significant decrease in work hardening. The results are compared to our latest
data that were obtained within a previous program (SPIRE), where T91 had also been irradiated in BR2
at 200 C (up to 2.6 dpa), and tested between 170 C and 300 C. Irradiation effects at lower irradiation
temperatures are more significant.
KW - T91
KW - mechanical properties
KW - neutron irradiation
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_89639
UR - http://knowledgecentre.sckcen.be/so2/bibref/5037
U2 - 10.1016/j.jnucmat.2008.02.063
DO - 10.1016/j.jnucmat.2008.02.063
M3 - Article
SN - 0022-3115
VL - 377
SP - 101
EP - 108
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1
ER -