Shenyang National Laboratory for Materials Science,Institute of Metal Research,Chinese Academy of Science,110016,Shenyang,China;
Key Laboratory of Nuclear Materials and Safety Assessment,Institute of Metal Research,Chinese Academy of Science,110016,Shenyang,China;
Nuclear Power and Petro-chemical Business Group,China First Heavy Industries,116113,Dalian,China;
Shenyang National Laboratory for Materials Science,Institute of Metal Research,Chinese Academy of Science,110016,Shenyang,China;
Key Laboratory of Nuclear Materials and Safety Assessment,Institute of Metal Research,Chinese Academy of Science,110016,Shenyang,China;
CAP1400; Residual stress; Safe-end; Nozzle; Numerical simulation;
机译:剩余寿命自动监控系统在解决水冷式水反应堆核电厂运行问题中的应用
机译:CAP1400核电站安全注入罐用SA-533 B型CL.1 + SA-240型304L压焊复合钢板的研制
机译:基于残余应力分析的核电站加压安全喷嘴一次水应力腐蚀开裂可能性的评估
机译:CAP1400核电厂反应堆中安全终端/喷嘴的残余应力预测
机译:通过实验确定CANDURTM核反应堆中滚动扩展接头的残余应力。
机译:在福岛第一核电站反应堆厂房内检测源自核燃料的α粒子发射器
机译:核电厂异种金属喷嘴对接焊缝残余应力分布的预测
机译:反应堆安全研究:美国商业核电厂事故风险评估。附录七。反应堆事故中放射性的释放。附录八。反应堆熔毁事故中的物理过程。附录九。核电厂安全设计理念。附录X.设计充分性。