奥氏体钢辐照促进应力腐蚀开裂行为机制的研究进展

doi:10.11902/1005.4537.2023.287

中国腐蚀与防护学报

2024, Vol. 44

Issue (4): 835-846 CSTR: 32134.14.1005.4537.2023.287 DOI: 10.11902/1005.4537.2023.287

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奥氏体钢辐照促进应力腐蚀开裂行为机制的研究进展

高俊宣¹, 曹晗¹(

), 匡文军²(

), 郑全¹, 张鹏¹, 钟巍华¹

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

Research Progress on Irradiation Assisted Stress Corrosion Cracking Behavior and Mechanism of Austenitic Steel

GAO Junxuan¹, CAO Han¹(

), KUANG Wenjun²(

), ZHENG Quan¹, ZHANG Peng¹, ZHONG Weihua¹

1. China Institute of Atomic Energy, Beijing 102413, China
2. School of Materials Science and Engineering, Xi'an Jiaotong University, Xi'an 710049, China

引用本文:

高俊宣, 曹晗, 匡文军, 郑全, 张鹏, 钟巍华. 奥氏体钢辐照促进应力腐蚀开裂行为机制的研究进展[J]. 中国腐蚀与防护学报, 2024, 44(4): 835-846.
Junxuan GAO, Han CAO, Wenjun KUANG, Quan ZHENG, Peng ZHANG, Weihua ZHONG. Research Progress on Irradiation Assisted Stress Corrosion Cracking Behavior and Mechanism of Austenitic Steel[J]. Journal of Chinese Society for Corrosion and protection, 2024, 44(4): 835-846.

全文: PDF(3825 KB) HTML

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。

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

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-pressure water medium in the primary coolant circuit, the low stress brittle cracking phenomenon, namely irradiation 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-initiation, crack-growth and cracking-sensitivity of IASCC are summarized. Then the main influence mechanisms of localized deformation, grain boundary oxidation, irradiation hardening, irradiation induced segregation (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 summarized. 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.

Key words： crack initiation and growth IASCC sensitivity localized deformation GB oxidation irradiation hardening irradiation induced segregation irradiation swelling and irradiation creep irradiation induced phase transformation post-irradiation annealing

收稿日期: 2023-09-10 32134.14.1005.4537.2023.287

ZTFLH:

TG172

基金资助:国家重点研发计划(2019YFB1900902)

通讯作者: 曹晗，E-mail：caohan@ciae.ac.cn，研究方向为反应堆材料腐蚀与防护、材料辐照效应等；
匡文军，E-mail：wjkuang66@xjtu.edu.cn，研究方向为核材料环境损伤及新材料研发

Corresponding author: CAO Han, E-mail: caohan@ciae.ac.cn;

作者简介: 高俊宣，男，1999年生，硕士生

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图1 IASCC数据中CGR与屈服应力的剂量依赖性[15]

图2 IASCC数据中CGR随应力强度因子和辐照温度的变化规律[16]

图3 中子辐照IASCC敏感性参数随剂量的变化[10,19]

图4 DC-GB位置处的法向应力及开裂情况统计[23,24]

图5 δ相对裂纹扩展的影响机理图[74]

图6 IASCC敏感性和材料辐照诱导的特征随退火条件的变化图[86]

图7 微观缺陷与力学性能随退火条件的变化[79,85]

图8 辐照至5.9 dpa的304L不锈钢在不同退火条件和不同水环境下的裂纹扩展速率[54]

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