Separation of microstructural and microchemical effects in irradiation assisted stress corrosion cracking using post-irradiation annealing

被引:56
作者
Fukuya, K
Nakano, M
Fujii, K
Torimaru, T
Kitsunai, Y
机构
[1] Inst Nucl Safety Syst, Fukui 9191205, Japan
[2] Nippon Nucl Fuel Dev Co Ltd, Oarai, Ibaraki 3111313, Japan
关键词
irradiation assisted stress corrosion cracking; stainless steel; grain boundary segregation; hardening; microstructural change; hydrogenated water; neutron irradiation;
D O I
10.3327/jnst.41.1218
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Post-irradiation annealing (PIA) was conducted in order to clarify the role of microstructural and microchemical effects on irradiation assisted stress corrosion cracking (IASCC) susceptibility in simulated pressurized water reactor (PWR) primary water. Microstructures, hardening, radiation-induced segregation and IASCC susceptibility were examined in cold-worked SUS 316 stainless steels irradiated to 25 dpa in a PWR after annealing at 673-823 K for 1 h. IASCC susceptibility, microstructures and hardening recovered as the annealing temperature increased whereas the grain boundary segregation of Cr and Ni remained almost unchanged. The results suggested that the change in IASCC susceptibility due to annealing is not attributed to the change in grain boundary segregation but to the change in microstructures and hardening. The fact that a smaller recovery of radiation hardening caused a larger IASCC susceptibility suggested that a threshold hardening level exists for the occurrence of IASCC.
引用
收藏
页码:1218 / 1227
页数:10
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