[1]王润中,徐超亮,贾文清,等.反应堆压力容器钢辐照损伤研究进展[J].中国材料进展,2026,45(11):020-29.
　WANG Runzhong,XU Chaoliang,JIA Wenqing,et al.Recent Progress on Irradiation Damage of Reactor Pressure Vessel Steel[J].MATERIALS CHINA,2026,45(11):020-29.
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反应堆压力容器钢辐照损伤研究进展()

中国材料进展[ISSN:1674-3962/CN:61-1473/TG]

卷:
45
期数:
2026年11
页码:
020-29
栏目:
出版日期:
2026-10-31

文章信息/Info

Title:
Recent Progress on Irradiation Damage of Reactor Pressure Vessel Steel
作者:
王润中;  徐超亮;  贾文清;  全琪炜;  刘向兵
苏州热工研究院有限公司，江苏 苏州 215004
Author(s):
WANG Runzhong;  XU Chaoliang;  JIA Wenqing;  QUAN Qiwei;  LIU Xiangbing
Suzhou Nuclear Power Research Institute Co., Ltd., Suzhou, Jiangsu, 215004, China
关键词:
反应堆压力容器钢; 辐照硬化/脆化; NiMnSi团簇; 辐照脆化预测方程; 辐照损伤缓解技术; 无损检测技术
Keywords:
Reactor pressure vessel steel;  Irradiation hardening/embrittlement;  NiMnSi clusters;  Prediction model on irradiation embrittlement;  Irradiation damage mitigation technology;  Non-destructive testing technology
分类号:
TL341
文献标志码:
A
摘要:
本文系统梳理反应堆压力容器（RPV）钢辐照损伤领域近年来的研究进展，并展望该领域后续研发方向。辐照诱发材料硬化与脆化问题，是制约核电站长期安全可靠运行、机组服役延寿的关键限制性因素。在辐照环境下，低铜低磷现代国产RPV 钢会在内部生成位错环与纳米溶质团簇，是造成其辐照硬化、脆化的最主要微观诱因。随着全球核电机组逐步向着80年长周期服役目标推进，NiMnSi团簇作为RPV钢服役后期主导的析出型缺陷，其演化行为及力学性能调控机制已成为当前领域的研究重点与技术难点。亟待厘清的核心科学问题包括：NiMnSi团簇大量析出的辐照注量阈值、缺陷演化与材料脆化硬化的耦合作用机制，以及镍、锰等主合金元素对团簇析出过程的调控规律。本综述旨在聚焦微观损伤机制研究与国产预测模型体系建立，同时综述了辐照脆化缓解技术与多参量先进无损检测技术的研发进展与机理关联，可为RPV钢辐照损伤机理研究、高可靠度辐照脆化预测模型构建、新型无损检测技术开发以及耐辐照新型合金设计提供理论依据与参考。
Abstract:
This paper provides a comprehensive review of recent advancements in the study of irradiation damage in reactor pressure vessel (RPV) steel and explores potential future research directions. Irradiation-induced hardening and embrittlement represent critical challenges that limit the long-term safety operation and life extension of nuclear power plants. Under irradiation,dislocation loops and nano-sized solute clusters form within low-copper and low-phosphorus domestic RPV steels, which are primarily responsible for the microstructural origins of irradiation-induced hardening and embrittlement. In response to the global demand for extending the operational lifespan of nuclear units to 60-80 years, NiMnSi clusters have emerged as the predominant precipitated defects during the end of RPV steel service lifetime,thus becoming a focal point of research and a significant technical challenge. Key scientific issues requiring elucidation include determining the fluence threshold for the extensive precipitation of NiMnSi clusters,understanding the coupling mechanisms between defect evolution and irradiation-induced hardening/embrittlement, and assessing the regulatory effects of primary alloying elements (such as Ni and Mn) on cluster precipitation behavior. This paper synthesizes the historical development of domestic irradiation embrittlement prediction models for RPV steels and reviews contemporary advancements in irradiation embrittlement mitigation technologies and sophisticated multi-parameter non-destructive testing methods, grounded in a fundamental understanding of microscale damage mechanisms. This review aims to provide theoretical support and technical references for elucidating the irradiation damage mechanisms of RPV steels,establishing high-reliability irradiation embrittlement prediction models,developing advanced non-destructive testing technologies, and designing high-performance materials.
更新日期/Last Update: 2026-09-28