The effect of post-irradiation annealing on the stress corrosion crack growth rate of neutron-irradiated 304L stainless steel in boiling water reactor environment

被引：25

作者：

Kuang, Wenjun ^{[1
,2
]}

Hesterberg, Justin ^{[2
]}

Was, Gary S. ^{[2
]}

机构：

[1] Xi An Jiao Tong Univ, Ctr Adv Mat Performance Nanoscale CAMP Nano, State Key Lab Mech Behav Mat, Xian 710049, Shaanxi, Peoples R China

[2] Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA

来源：

CORROSION SCIENCE | 2019年 / 161卷

关键词：

Stainless steel; SEM; Stress corrosion; Reactor conditions; Segregation; DEFECT STRUCTURE; DIFFUSION; BEHAVIOR;

D O I：

10.1016/j.corsci.2019.108183

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The effect of post-irradiation annealing (PIA) on the irradiation-assisted stress corrosion cracking (IASCC) of 304L stainless steel in boiling water reactor environments was studied. PIA has little effect on the crack growth rate (CGR) in normal water chemistry even it restored most of the irradiation-induced microstructure change. Nevertheless, PIA can significantly suppress the CGR in hydrogen water chemistry (HWC). The mitigation factor of HWC increases with the degree of PIA up to 5h at 550 degrees C and correlates with the recovery of Si segregation at grain boundary. PIA is an effective strategy for decreasing IASCC susceptibility in reducing water environment.

引用

页数：9

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