| METALS AND METAL MATRIX COMPOSITES |
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| Review of the Effect of Irradiation-Assisted Stress Corrosion Cracking on Stainless Steel in Light Water Reactor Environments |
| XU Chaoliang1,2,4, QUAN Qiwei2,4, WU Huanchun2,4, LI Yuanfei2,4, JIA Wenqing2,4, YIN Jian2,4, LI Shilei3, SONG Miao1, ZHANG Lefu1, LIU Xiangbing2,4,*, GUO Xianglong1,*
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1 School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
2 Material Engineering Center, Suzhou Nuclear Power Research Institute Co., Ltd., Suzhou 215004, Jiangsu, China
3 State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing, Beijing 100083, China
4 National Engineering Research Center for Nuclear Power Plant Safety & Reliability, Suzhou 215004, Jiangsu, China |
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Abstract Stainless steel materials used in the internal components of light water reactors (LWRs) operate under conditions of high temperature, high irradiation,and reactor primary water environment. Irradiation-assisted stress corrosion cracking (IASCC) is the primary failure mechanism, leading to multiple fracture incidents in reactor internals. Through investigation and analysis, this summary introduces the irradiation environment in LWRs. Then an analysis is given about the impact of irradiation on the microstructure and hardness, micro-regional chemical elements, electrochemical corrosion potential (ECP) of the primary water, temperature, and stress in stainless steel. Furthermore, the influence patterns of these factors on IASCC is summarized.
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Published: 10 January 2026
Online: 2026-01-09
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2026, Vol. 40 
