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反应堆压力容器钢韧性评价及韧脆转变机理的研究进展
          
Research Progress on Toughness Evaluation and of Ductile-Brittle Transition Mechanism of Reactor Pressure Vessel Steel

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。
标    签 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  
 
Abstract
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.

中图分类号 TL341   DOI 10.11973/jxgccl202107002

 
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基金项目 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)

收稿日期 2020/7/8

修改稿日期 2021/5/18

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备注饶德林(1965-),男,江西南昌人,副研究员,博士

引用该论文: RAO Delin,MO Jiahao,GAO Jianbo,LI Jun,ZHANG Shuyan. Research Progress on Toughness Evaluation and of Ductile-Brittle Transition Mechanism of Reactor Pressure Vessel Steel[J]. Materials for mechancial engineering, 2021, 45(7): 7~11
饶德林,莫家豪,高建波,李军,张书彦. 反应堆压力容器钢韧性评价及韧脆转变机理的研究进展[J]. 机械工程材料, 2021, 45(7): 7~11


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