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

Wenjun Kuang; Justin Hesterberg; Gary S. Was

doi:10.1016/j.corsci.2019.108183

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

Wenjun Kuang
, Justin Hesterberg
, Gary S. Was

School of Materials Science and Engineering

University of Michigan, Ann Arbor

Research output: Contribution to journal › Article › peer-review

28 Scopus citations

Abstract

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 5 h at 550 °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.

Original language	English
Article number	108183
Journal	Corrosion Science
Volume	161
DOIs	https://doi.org/10.1016/j.corsci.2019.108183
State	Published - Dec 2019

Keywords

Reactor conditions
SEM
Segregation
Stainless steel
Stress corrosion

Access to Document

10.1016/j.corsci.2019.108183

Cite this

@article{0813fc218d624a11b74b7d87291727a5,

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

abstract = "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 5 h at 550 °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.",

keywords = "Reactor conditions, SEM, Segregation, Stainless steel, Stress corrosion",

author = "Wenjun Kuang and Justin Hesterberg and Was, \{Gary S.\}",

note = "Publisher Copyright: {\textcopyright} 2019 Elsevier Ltd",

year = "2019",

month = dec,

doi = "10.1016/j.corsci.2019.108183",

language = "英语",

volume = "161",

journal = "Corrosion Science",

issn = "0010-938X",

publisher = "Elsevier Ltd",

}

TY - JOUR

T1 - The effect of post-irradiation annealing on the stress corrosion crack growth rate of neutron-irradiated 304L stainless steel in boiling water reactor environment

AU - Kuang, Wenjun

AU - Hesterberg, Justin

AU - Was, Gary S.

PY - 2019/12

Y1 - 2019/12

N2 - 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 5 h at 550 °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.

AB - 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 5 h at 550 °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.

KW - Reactor conditions

KW - SEM

KW - Segregation

KW - Stainless steel

KW - Stress corrosion

UR - https://www.scopus.com/pages/publications/85070876269

U2 - 10.1016/j.corsci.2019.108183

DO - 10.1016/j.corsci.2019.108183

M3 - 文章

AN - SCOPUS:85070876269

SN - 0010-938X

VL - 161

JO - Corrosion Science

JF - Corrosion Science

M1 - 108183

ER -

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

Abstract

Keywords

Access to Document

Other files and links

Fingerprint

Cite this