奥氏体钢辐照促进应力腐蚀开裂行为机制的研究进展
Research Progress on Irradiation Assisted Stress Corrosion Cracking Behavior and Mechanism of Austenitic Steel
高俊宣 1曹晗 1匡文军 2郑全 1张鹏 1钟巍华1
作者信息
- 1. 中国原子能科学研究院 北京 102413
- 2. 西安交通大学材料科学与工程学院 西安 710049
- 折叠
摘要
奥氏体不锈钢是压水堆堆内构件的主要材料,服役过程中在中子辐照、拉应力和一回路高温高压水的联合作用下可发生辐照促进应力腐蚀开裂(IASCC),并导致部件断裂失效,从而影响堆芯构件结构完整性,已经成为影响核电站安全、经济运行的关键问题之一.本文通过调研总结,综述了辐照致IASCC裂纹萌生、扩展及敏感性变化的行为规律,分析了局部变形、晶界氧化、辐照硬化、辐照诱导偏析(RIS)、辐照肿胀及辐照蠕变、辐照诱导相变等主要IASCC机制,总结了辐照后退火(PIA)在IASCC机制研究中的应用,并讨论了 IASCC行为机理研究的发展趋势,以期为中子辐照IASCC的行为机理研究提供参考.
Abstract
Austenitic stainless steel is the main material for reactor core components.In the service process,under the joint action of neutron irradiation,tensile stress and high-temperature and high-pres-sure water medium in the primary coolant circuit,the low stress brittle cracking phenomenon,namely irra-diation assisted stress corrosion cracking(IASCC)can occur,which will lead to component fracture and failure,thus affecting the structural integrity of reactor core components.This has become one of the key issues affecting the safety and economic operation of nuclear power plants.In this paper,the crack-initia-tion,crack-growth and cracking-sensitivity of IASCC are summarized.Then the main influence mecha-nisms of localized deformation,grain boundary oxidation,irradiation hardening,irradiation induced segre-gation(RIS),irradiation swelling,irradiation creep and irradiation induced phase transformation on IASCC are analyzed.Meanwhile,the application of post-irradiation annealing(PIA)for resolving IASCC is sum-marized.Finally,the prospect of research on IASCC mechanism is discussed.This review is aimed to provide a reference for understanding the issue of neutron irradiation assisted stress corrosion cracking of austenitic stainless steels.
关键词
裂纹萌生与扩展/IASCC敏感性/局部变形/晶界氧化/辐照硬化/辐照诱导偏析/辐照肿胀与辐照蠕变/辐照诱导相变/辐照后退火Key words
crack initiation and growth/IASCC sensitivity/localized deformation/GB oxidation/irra-diation hardening/irradiation induced segregation/irradiation swelling and irradiation creep/irradiation induced phase transformation/post-irradiation annealing引用本文复制引用
基金项目
国家重点研发计划(2019YFB1900902)
出版年
2024
NETL
NSTL
万方数据