核能系统压力容器辐照脆化机制及其影响因素

doi:10.11900/0412.1961.2014.00189

金属学报

2014, Vol. 50

Issue (11): 1285-1293 DOI: 10.11900/0412.1961.2014.00189

本期目录 | 过刊浏览

核能系统压力容器辐照脆化机制及其影响因素

李正操(

), 陈良

清华大学材料学院先进材料教育部重点实验室, 北京 100084

IRRADIATION EMBRITTLEMENT MECHANISMS AND RELEVANT INFLUENCE FACTORS OF NUCLEAR REACTOR PRESSURE VESSEL STEELS

LI Zhengcao(

), CHEN Liang

Advanced Materials Laboratory, Ministry of Education, School of Materials Science and Engineering, Tsinghua University, Beijing 100084

引用本文:

李正操, 陈良. 核能系统压力容器辐照脆化机制及其影响因素[J]. 金属学报, 2014, 50(11): 1285-1293.
Zhengcao LI, Liang CHEN. IRRADIATION EMBRITTLEMENT MECHANISMS AND RELEVANT INFLUENCE FACTORS OF NUCLEAR REACTOR PRESSURE VESSEL STEELS[J]. Acta Metall Sin, 2014, 50(11): 1285-1293.

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摘要:

核反应堆压力容器作为核电站不可更换的关键性设备, 其设备完整性对核电站的安全运行起着至关重要的作用. 在辐照条件下, 反应堆压力容器钢中会形成一系列微结构缺陷, 包括溶质沉淀、基体损伤和脆性元素的晶界偏聚等, 导致材料的韧脆性转变温度升高, 产生辐照脆化效应. 而压力容器钢的成分和辐照条件决定了各种微结构对辐照脆化的贡献大小. 本文主要针对核能系统压力容器辐照脆化机制及其影响因素进行了综述, 总结讨论了这些微结构的形成机制及溶质元素、辐照通量和辐照后退火对这些微结构和材料机械性能的影响, 并指出了存在的问题和未来的研究方向.

关键词 ：反应堆压力容器, 辐照脆化, 溶质沉淀, 基体损伤, 晶界偏聚

Abstract：

Nuclear reactor pressure vessel is the irreplaceable component of the nuclear power plant and its integrity is one of the key issues of any nuclear power plant for long term operations. Various nanofeatures, including solute clusters, matrix damage and grain boundary segregation formed in reactor pressure vessel steels in the face of neutron irradiation. These ultrafine microstructural features lead to an increase in the ductile brittle transition temperature as is the measure used to describe the irradiation embrittlement. The balance of features depends on the composition of the reactor pressure vessel steels and the irradiation conditions. This paper reviews the current phenomenological knowledge and understanding of the basic mechanisms and relevant influence factors for irradiation embrittlement of nuclear reactor pressure vessel steels. To be specific, the formation and evolution processes of the embrittling features are presented. Also, the influences of material variables, such as copper, nickel and manganese contents on irradiation embrittlement and those of irradiation variables, such as neutron flux and post irradiation annealing are summarized. In addition, fundamental research issues that remain to be addressed are briefly pointed out.

Key words： reactor pressure vessel irradiation embrittlement solute precipitation matrix damage grain boundary segregation

收稿日期: 2014-06-26

ZTFLH:

TL341

基金资助:* 国家科技重大专项资助项目2011ZX06004-002

作者简介: null

李正操, 男, 1975年生, 副教授

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图1 压水堆核电站Doel-1和Doel-2辐照监督试样溶质原子分布图[22]

图2 Fe-1.1Mn-0.7Ni (原子分数, %)合金在中子辐照剂量为0.2 dpa时的三维原子探针(APT)实验结果[54]

图3 Fe-1.2Mn-0.7Ni (原子分数, %)合金经过0.024 dpa中子辐照所产生的沉淀物的成分分布[52]

图4 经过0.2 dpa中子辐照的纯Fe的TEM像[54]

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