摘要
核电关键设备及构筑物的服役寿命预测是制约核电站安全评价及延寿论证的技术瓶颈。目前,国内核电关键材料老化机理研究不够深入、基础试验数据相对缺乏、多因素耦合寿命预测自主模型不足。针对以上问题,本文以反应堆压力容器、堆内构件紧固螺栓、一回路重要镍基合金部件及主管道、安全壳及堆坑混凝土等关键设备和重要构筑物为研究对象,探究部件材料高通量辐照损伤、辐照促进应力腐蚀、疲劳损伤等材料性能退化行为,揭示核电环境高温高压水—辐照—应力等多因素耦合条件下关键设备及构筑物服役老化机理及行为规律,以期建立核电关键部件寿命预测模型和分析程序。
The life evaluation of key equipment and concrete structures is the significance problem which restricts the safety evaluation and life extension of the nuclear power plants in China.At present,there was no further research on aging mechanism of the nuclear power materials in China,basic test data was seriously lacking,and the independent model of multi-factor coupling life prediction was not enough.For the above questions,the reactor pressure vessel,the fastening bolts of the reactor internal components,the nickel-based alloy parts and main pipe materials of the primary circuit are chosen as the study objects.The effects of high flux irradiation damage,irradiation assisted stress corrosion cracking(IASCC)and fatigue on the degradation of the nuclear key materials were studied.The purpose of the studies is to reveal the aging and degradation mechanism and behavior rules of the materials of key equipment and concrete structures under the coupled conditions of high temperature and high pressure water,irradiation and stress in nuclear power environment,then establish the life prediction model and analysis program of key material components in nuclear power.
作者
孙海涛
孙造占
陈银强
李吉娃
刘超
孟凡江
郭彦辉
SUN Haitao;SUN Zaozhan;CHEN Yinqiang;LI Jiwa;LIU Chao;MENG Fanjiang;GUO Yanhui(Nuclear and Radiation Safety Center,Beijing 100082;China Nuclear Power Operation Technology Co.,Ltd.,Wuhan 430223;Central Research Institute of Building and Construction(Shenzhen)Co.,Ltd.,Shenzhen 518000;China Institute of Atomic Energy,Beijing 102413;Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.,Shanghai 200233)
出处
《中国基础科学》
2021年第3期34-41,共8页
China Basic Science
基金
国家重点研发计划项目(2019YFB1900900)。
关键词
核电站
反应堆压力容器
堆内构件
安全壳
老化机制
寿命预测
nuclear power plant
reactor pressure vessel
reactor internals
containment vessel
aging mechanism
life evaluation
