Intergranular cracking mechanism in baffle former bolt materials for PWR core internals

被引:2
|
作者
Yonezawa, T
Arioka, K
Kanasaki, H
Fujimoto, K
Ajiki, K
Matsuoka, T
Urata, S
Mizuta, H
机构
来源
关键词
PWR type reactors; stainless steels; IASCC; stress corrosion cracking; grain boundaries; carbides; core internals; PWSCC; pH value;
D O I
10.3327/jaesj.42.212
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
In this study, the cause of intergranular cracking in baffle former bolts (BFBs) was estimated from metallurgical and chemical viewpoints based upon the experimental data and information published by EdF. At first, five kinds of possibilities were estimated as the cause of intergranular cracking in BFBs. Five possibilities estimated were (1) mechanical cracking caused by high strain in irradiation hardened austenitic stainless steels, (2) O-2 SCC due to residual oxygen in the bolt stagnant region, (3) caustic SCC due to dry and wet phenomenon, (4) low pH SCC due to oxygen concentration cell, and (5) PWSCC due to radiation induced segregation. In this study each possibility was evaluated by the calculation and some out of pile tests. And also, the cause of the intergranular cracking in BFBs was estimated by the data of the post-irradiation examinations and basic out of pile tests for Type 316CW and Type 347 stainless steels in the authors' previous study. From these evaluation, the intergranular cracking in BFBs seems to be caused by the PWSCC, but not caused by mechanical cracking Oz SCC, caustic SCC or low pH SCC.
引用
收藏
页码:212 / 217
页数:6
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