核电厂反应堆压力容器材料辐照脆化研究进展综述  

A Comprehensive Review of Research Progress on Irradiation Embrittlementof Reactor Pressure Vessel Materials in Nuclear Power Plant

作　　者：岳鹏 刘娟波 成雷 白学刚 Yue Peng;Liu Juanbo;Cheng Lei;Bai Xuegang(Science and Technology on Particle Transport and Separation Laboratory,Tianjin 300180;China Special Equipment Inspection and Research Institute,Beijing 100029)

机构地区：[1]粒子输运与富集技术重点实验室,天津300180 [2]中国特种设备检测研究院,北京100029

出　　处：《科技风》2023年第13期1-3,共3页

摘　　要：反应堆压力容器是核电机组运行中操作条件最为苛刻的部件,长期承受高温、高压、快中子的高强度辐照,会出现辐照脆化现象。该文针对核电机组RPV辐照脆化问题,阐述了RPV钢材料的发展路径与工艺特点,总结了国产RPV用钢的研究历程与应用情况。基于对辐照脆化微观机理的分析,探讨了材料化学成分、微观组织特性、晶粒尺寸、辐照温度、中子注量、中子注量率以及中子能谱等因素对韧脆转变温度的影响,进一步明确了辐照脆化评价的方法及局限性,讨论了参数化预测与结构化预测模型的优缺点。结构化预测模型能够很好地解释材料脆化特征与脆化机理之间的关系,对本质上理解辐照脆化效应并改进RPV材料的设计制造具有重要意义。Reactor Pressure Vessel is a critical component in Nuclear power plant,which usually suffers severest irradiation condition with elevated temperature and pressure,thus displaying irradiation embrittlement phenomenon.Aimed at this problem,the evolution path and process feature of RPV material were firstly reviewed in this article.Besides,the research course and application situation of domestic RPV steel were summarized.Based on the microscopic embrittlement mechanism comprehensive analysis,the affecting factors including chemical composition,microscopic structure,grain size,irradiation temperature,neutron fluence,neutron fluence rate and neutron spectrum on ductile brittle transition temperature were further discussed.Moreover,a detailed description about how to estimate irradiation embrittlement was exhibited to demonstrate its limitations.The strengths and weaknesses of both empirical prediction model and structural evaluation model were also pointed out.The structural evaluation model can well explain the relationship between embrittlement characteristics and mechanism of RPV,which is of great significance for essentially understanding irradiation embrittlement to improve its design and manufacture.

关 键 词：反应堆压力容器 辐照脆化 影响因素 脆化机制 预测模型 

分 类 号：TL3[核科学技术—核技术及应用]