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秦山核电厂反应堆压力容器辐照脆化时限老化分析 被引量:2

Irradiation Embrittlement Time-limited Aging Analysis of Reactor Pressure Vessel for Qinshan Nuclear Power Plant
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摘要 反应堆压力容器是核电厂最重要设备之一,其辐照脆化状态决定了核电厂的实际运行寿命。通过借鉴国外反应堆压力容器安全评估方法,开发出一套反应堆压力容器辐照脆化时限老化分析(TLAA)的方法。该方法从上平台能量、反应堆运行压力-温度曲线及承压热冲击3个方面评价压力容器材料在正常工况和事故工况下的安全裕度。采用该方法在秦山核电厂运行许可证延续(OLE)项目中对反应堆压力容器进行了辐照脆化TLAA安全评估,其评估方法和评估结论到得国家核安全监管局的认可,为秦山核电厂延寿20 a奠定了基础。 Reactor pressure vessel is one of the most important equipment in nuclear power plant,and its irradiation embrittlement state determines the actual operation life of nuclear power plant.A method of irradiation embrittlement time-limited aging analysis(TLAA)for reactor pressure vessel is developed by referring to foreign reactor pressure vessel safety assessment methods.This method evaluates the safety margin of pressure vessel materials under normal and accident conditions from three aspects:upper platform energy,reactor operating pressuretemperature curve and pressure bearing thermal shock.Using this method,the irradiation embrittlement TLAA safety evaluation of the reactor pressure vessel is carried out in the Qinshan Nuclear Power Plant Operation License Extension(OLE)Project.Its evaluation methods and evaluation conclusions have been recognized by the National Nuclear Safety Administration,laying the foundation for the 20-year life extension of Qinshan NPP.
作者 栾兴峰 赵传礼 许锋 陶宏新 张江涛 高轩 陶革 Luan Xingfeng;Zhao Chuanli;Xu Feng;Tao Hongxin;Zhang Jiangtao;Gao Xuan;Tao Ge(CNNP Nuclear Power Operations Management Co.,Ltd.,Haiyan,Zhejiang,314300,China;Shanghai Nuclear Engineering Research and Design Institute,Shanghai,200030,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2022年第S01期51-54,共4页 Nuclear Power Engineering
关键词 压水堆 辐照脆化 时限老化分析(TLAA) 运行许可证延续(OLE) Pressurized water reactor Irradiation embrittlement Time-limited aging analysis Operation licence extention(OLE)
作者简介 栾兴峰(1979-),男,硕士研究生,现主要从事核电厂老化和延寿管理的研究,E-mail:luanxf@cnnp.com.cn。
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  • 2ASME boiler & pressure vessel Code[S], Section III. Division I, Subsection NB, "Class 1 Components", 1998 Edition.
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