某核电厂RPV辐照脆化性能预测与延续运行评估  

Prediction of RPV Irradiation Embrittlement Performance and Life Evaluation of Extended Operation in a Nuclear Power Plant

作　　者：房永刚 佟振峰 初起宝 曾珍 慎英才 Fang Yonggang;Tong Zhenfeng;Chu Qibao;Zeng Zhen;Shen Yingcai(Nuclear and Radiation Safety Center,MEE,Beijing,100082,China;North China Electric Power University,Beijing,102206,China)

机构地区：[1]生态环境部核与辐射安全中心,北京100082 [2]华北电力大学,北京102206

出　　处：《核动力工程》2023年第4期192-197,共6页Nuclear Power Engineering

基　　金：国家重点研发计划项目(2019YFB1900900)。

摘　　要：我国自主设计建造的某核电厂已进入延续运行阶段,作为反应堆核心部分的压力容器辐照脆化性能评价采用了国外的辐照脆化预测模型,但该模型基于的辐照数据不能有效代表我国反应堆压力容器(RPV)材料的辐照脆化性能,尤其是针对延续运行阶段。本文基于国内外RPV辐照脆化预测模型及其开发机理,构建了适用于我国工程应用的自主低Cu RPV辐照脆化预测模型,该模型考虑了稳定基体缺陷和合金元素析出沉淀等辐照脆化关键因素,同时根据国产低Cu RPV材料的辐照脆化数据,开展了自主模型的标准偏差和裕量分析,结果表明模型预测置信度较高。最后依据自主模型评估该核电厂RPV的辐照脆化性能,证明其延续运行至60等效满功率年(EFPY)具有可行性。A domestic self-designed and built nuclear power plant has entered the stage of extended operation.A foreign prediction model was adopted for the irradiation embrittlement evaluation of the reactor pressure vessel,however,the irradiation data on which the foreign prediction model was based cannot effectively represent the irradiation embrittlement performance of domestic RPV materials,especially for the extended operation stage.Based on the radiation embrittlement prediction models of RPV at home and abroad and their development mechanisms,an independent low-Cu RPV radiation embrittlement prediction model suitable for domestic engineering applications has been formed,which considers the key factors of irradiation embrittlement such as stable matrix defects and alloy element precipitation.According to the irradiation embrittlement data of domestic low-Cu RPV materials,the standard deviation and margin analysis of the independent model were carried out,and the results indicated a high level of confidence in prediction.Based on the model,the irradiation performance of the RPV was evaluated,and the feasibility of extended operation to 60 equivalent full power years(EFPY)was demonstrated.

关 键 词：压力容器 辐照脆化 预测模型 延续运行 

分 类 号：TL48[核科学技术—核技术及应用]