材料辐照脆化模型对田湾反应堆压力容器的适应性研究  

Research on the Adaptability of Material Irradiation Embrittlement Model to Tianwan Reactor Pressure Vessel

作　　者：詹乐昌 张永新 吴超平[1] 包捷 常亮明[1] ZHANG Yong-Xin;WU Chao-Ping;BAO Jie;CHANG Liang-Ming(China Productivity Center For Machinery Co.,Ltd.,Beijing100044,China)

机构地区：[1]中机生产力促进中心有限公司,北京100044

出　　处：《机电产品开发与创新》2023年第3期26-28,35,共4页Development & Innovation of Machinery & Electrical Products

摘　　要：反应堆压力容器(RPV)是核电站不可更换的关键设备,其材料的退化(辐照脆化和热老化)决定着它的使用寿命。田湾核电厂RPV属俄罗斯VVER-1000/428型,其母材和焊缝是含Ni较高的Cr-Mo-V钢。本文应用俄罗斯和乌克兰提出的材料辐照脆化新模型对田湾核电厂RPV进行评价,结果表明:该模型比原俄罗斯评价模型的温度裕量提高了两倍多。对新评价模型Ni,Mn和Si含量的随机影响分析表明,新评价模型中增加的分散度是材料标准差的7倍,可见置信度足够高;对该模型与美国、法国和日本等国6种评价辐照脆化方法的比较表明:除法国外,该模型比日本和美国RG1.99的Rev.1和Rev.2、NUREG/CR-6551和NUREG/CR-6584等5种评价方法都保守。The reactor pressure vessel(RPV)is a key equipment that cannot be replaced in a nuclear power plant.The degradation of its materials(irradiation embrittlement and thermal aging)determines its service life.Tianwan Nuclear Power Plant RPV belongs to Russian VVER-1000/428 type.Its base metal and weld seam is Cr-Mo-V steel with higher Ni content.This paper applies the new radiation embrittlement model proposed by Russia and Ukraine to evaluate the RPV of Tianwan Nuclear Power Plant,the results show that this model more than doubles the temperature margin of the original Russian evaluation model.An analysis of the random effects of the Ni,Mn,and Si contents of the new evaluation model shows that the increased dispersion in the new evaluation model is 7 times the standard deviation of the material,and the visible confidence is high enough.The comparison of this model with six evaluation methods for radiation embrittlement in the United States,France,and Japan shows that:except for France,this model is much better conservative than the RG1.99,the Rev.1 and Rev.2 of NUREG/CR-6551,the NUREG/CR-6584.and Japan such five evaluation methods.

关 键 词：压力容器 寿命 辐照脆化 置信度 

分 类 号：F416.23[经济管理—产业经济]