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作 者:陈明亚[1,2] 曹昱澎 贺寅彪[3] 孙欣[4] 余伟炜 史方杰[1,2] 彭群家 赵万祥 CHEN Mingya;CAO Yupeng;HE Yinbiao;SUN Xin;YU Weiwei;SHI Fangjie;PENG Qunjia;ZHAO Wanxiang(Suzhou Nuclear Power Research Institute,Suzhou 215000,China;National Nuclear Power Plant Safety and Reliability Engineering Research Center,Suzhou 215004,China;Shanghai nuclear engineering research and design institute,Shanghai 200233,China;Zhejiang Shuren University,Hangzhou 310015,China)
机构地区:[1]苏州热工研究院有限公司,江苏苏州215000 [2]国家核电厂安全及可靠性工程技术研究中心,江苏苏州215004 [3]上海核工程研究设计院股份有限公司,上海200233 [4]浙江树人大学,杭州310015
出 处:《压力容器》2023年第12期50-58,共9页Pressure Vessel Technology
基 金:国家重点研发计划项目(2020YFB1901500,2021YFB3702602)。
摘 要:针对厚壁反应堆压力容器(RPV)辐照脆化后的含缺陷结构完整性评定(简称“评定”)是核电厂长寿期运行安全论证中的关键技术难点,综述了国际上在厚壁含缺陷RPV堆芯筒体段断裂测试分析的研究成果,并结合国际原子能机构和笔者团队相关的数值研究成果,论述了典型事故瞬态下RPV堆芯筒体段裂纹的启裂、止裂与撕裂性能,认为事故工况下,RPV中浅裂纹具有良好的止裂特性,基于开发的瞬态参数在线监测的评定技术,提出了基于瞬态参数在线监测的RPV辐照脆化断裂评定的方法。所探讨的评定技术对论证RPV长寿期安全运行特性具有参考价值。Structural integrity assessment(SIA)of thick-walled embrittled reactor pressure vessel(RPV)is one of the key technical issues in the verification of long-term operation of nuclear power plants.The research results of the fracture test of the thick-walled cracked RPV beltline in the world were reviewed.Combined with the numerical simulation research achievements of the International Atomic Energy Agency and the author′s team,the crack initiation,arrest and tearing characteristics of the RPV beltline under the typical accident transient were discussed.It is considered that the shallow cracks in RPV have good crack arrest characteristics under accident conditions.At the same time,based on the SIA technology for on-line monitoring of transient parameters,which is developed by the author′s team,a technical method for evaluating embrittled RPV based on on-line monitoring of transient parameters was proposed.The SIA technology discussed in this study has a reference value for demonstrating the safe characteristics of RPV in the long-life operation.
关 键 词:反应堆压力容器 辐照脆化 启裂 止裂 撕裂 在线评定
分 类 号:TH49[机械工程—机械制造及自动化] TB121[理学—工程力学]
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