摘要
反应堆压力容器(RPV)钢的力学性能评价是核电厂延寿评价的主要内容,其中辐照损伤引起的韧脆转变温度上升是影响运行安全和寿命的主要因素。RPV钢的韧脆转变评价通过抽取监督试样进行,但监督试样的短缺迫使材料工作者采用小试样和试样重组等技术研究韧性评价问题。对近年来国内外RPV钢的韧性评价方法进行了论述,介绍了几种无损检测技术在RPV钢力学性能检测方面的应用;着重介绍了近3 a来国内外在RPV钢辐照脆化机理,尤其是强辐照下组织结构演化机理的研究进展,最后对我国RPV钢韧性评价和相关机理研究进行了展望。
The evaluation of mechanical performance of reactor pressure vessel(RPV)steel is the main content of the life extension evaluation of nuclear power plants,and the increase of ductile-brittle transition temperature caused by irradiation damage is the main factor affecting operational safety and life.The toughness and brittleness transition evaluation of RPV steel is carried out by drawing surveillance samples,but the shortage of the surveillance samples forces material workers to study the toughness evaluation using small sample and sample reconstitution technique.The toughness evaluation methods of RPV steel at home and abroad in recent years are discussed,and the application of several nondestructive testing techniques on RPV steel mechanical property testing is described.The research progress on the irradiated embrittlement mechanism of RPV steels,especially the microstructure evolution mechanism of RPV steel under the high irradiation condition,in the past three years at home and abroad is described.Finally,the prospect of toughness evaluation and related mechanism research of RPV steel in China is presented.
作者
饶德林
莫家豪
高建波
李军
张书彦
RAO Delin;MO Jiahao;GAO Jianbo;LI Jun;ZHANG Shuyan(Centre of Excellence of Advanced Materials,Dongguan 523808,China;Science and Technologyon Reactor Fuel and Materials Laboratory,Nuclear Power Institute of China,Chengdu610213,China)
出处
《机械工程材料》
CAS
CSCD
北大核心
2021年第7期7-11,共5页
Materials For Mechanical Engineering
基金
广东省基础与应用基础研究重大项目(2019B030302011)
广东省引进创新创业团队项目(2016ZT06G025)
反应堆燃料及材料重点实验室稳定支持课题(JCKYS2019201073)。
关键词
反应堆压力容器钢
韧脆转变
析出相
辐照脆化
reactor pressure vessel steel
ductile-brittle transition
precipitate
irradiation embrittlement
作者简介
饶德林(1965-),男,江西南昌人,副研究员,博士。
