TY - JOUR
T1 - A study of the neutron irradiation effects on the susceptibility to embrittlement of A316L and T91 steels in lead–bismuth eutectic
AU - Sapundjiev, Danislav
AU - Al Mazouzi, Abderrahim
AU - Van Dyck, Steven
A2 - Sobolev, Vitaly
A2 - Schuurmans, Paul
N1 - Score = 10
PY - 2006/9/8
Y1 - 2006/9/8
N2 - The effects of neutron irradiation on the susceptibility to liquid metal embrittlement of two primary selected materials
for MYRRHA project an accelerator driven system (ADS), was investigated by means of slow strain rate tests (SSRT).
The latter were carried out at 200 C in nitrogen and in liquid Pb–Bi at a strain rate of 5 · 106 s1. The small tensile specimens
were irradiated at the BR-2 reactor in the MISTRAL irradiation rig at 200 C for 3 reactor cycles to reach a dose of
about 1.50 dpa. The SSR tests were carried out under poor and under dissolved oxygen conditions (1.5 · 1012 wt%
dissolved oxygen) which at this temperature will favour formation of iron and chromium oxides. Although both materials
differ in structure (fcc for A316L against bcc for T91), their flow behaviour in contact with liquid lead bismuth eutectic
before and after irradiation is very similar. Under these testing conditions none of them was found susceptible to liquid
metal embrittlement (LME).
AB - The effects of neutron irradiation on the susceptibility to liquid metal embrittlement of two primary selected materials
for MYRRHA project an accelerator driven system (ADS), was investigated by means of slow strain rate tests (SSRT).
The latter were carried out at 200 C in nitrogen and in liquid Pb–Bi at a strain rate of 5 · 106 s1. The small tensile specimens
were irradiated at the BR-2 reactor in the MISTRAL irradiation rig at 200 C for 3 reactor cycles to reach a dose of
about 1.50 dpa. The SSR tests were carried out under poor and under dissolved oxygen conditions (1.5 · 1012 wt%
dissolved oxygen) which at this temperature will favour formation of iron and chromium oxides. Although both materials
differ in structure (fcc for A316L against bcc for T91), their flow behaviour in contact with liquid lead bismuth eutectic
before and after irradiation is very similar. Under these testing conditions none of them was found susceptible to liquid
metal embrittlement (LME).
KW - LBE
KW - T91
KW - SS316
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_32554
UR - http://knowledgecentre.sckcen.be/so2/bibref/3639
U2 - 10.1016/j.jnucmat.2006.05.030
DO - 10.1016/j.jnucmat.2006.05.030
M3 - Article
SN - 0022-3115
VL - 356
SP - 229
EP - 236
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1-3
ER -