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作 者:赵延义 王泽武 范海贵 刘培启[1] ZHAO Yanyi;WANG Zewu;FAN Haigui;LIU Peiqi(School of Chemical Engineering,Dalian University of Technology,Dalian 116024,China)
出 处:《压力容器》2021年第12期53-61,共9页Pressure Vessel Technology
基 金:国家重点研发计划项目(2018YFA0704604)。
摘 要:核岛主系统发生严重失水事故后,需要启动非能动安全注入系统注水以快速冷却堆芯,但过大的热冲击载荷易引起直接安注(DVI)接管发生快速断裂。基于RCC-M ZG3210规定,在反应堆压力容器(RPV)筒体和DVI接管连接区构建了半椭圆形表面裂纹;开发了热力耦合作用下表面裂纹弹塑性断裂J积分的数值计算模型,并进行了验证分析和裂纹强度评定;探究了温差、裂纹深长比和双裂纹交互作用对J积分的影响规律。该研究成果不仅可用于评定核岛内DVI接管表面裂纹的安全性以及抗快速断裂能力,也可用于其他承压结构在热力耦合作用下表面裂纹弹塑性J积分计算分析。After a serious loss of coolant accident occurs in the main system of nuclear island,it is necessary to start the passive safety injection system to quickly cool the reactor core by injecting water,but excessive thermal shock load can easily lead to the rapid fracture of the direct vessel injection(DVI)nozzle.According to the RCC-M ZG3210,a semi-elliptic surface crack was established at the connection zone between the cylindrical shell of reactor pressure vessel(RPV)and DVI nozzle.Then,a numerical calculation model for the elasto-plastic J integral of the surface crack was developed under the thermal-mechanical coupling loads,and the verification analysis and crack strength evaluation were carried out.Finally,the effects of temperature difference,depth-length ratio of the crack and interaction of the double cracks on the J integral were discussed.The research results not only can be used for evaluating the safety and rapid fracture resistance of the DVI nozzle in the nuclear islands,but also can guide the calculation and analysis of the elastoplastic J integral in the surface cracks for other pressure structures under the thermos-mechanical coupling loads.
关 键 词:反应堆压力容器(RPV) 直接安注(DVI)接管 J积分 双裂纹 快速断裂
分 类 号:TH123[机械工程—机械设计及理论] TL351[核科学技术—核技术及应用]
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