Z箍缩驱动混合堆第一壁热-力学瞬态响应分析  

Thermal-mechanical response analysis of the first wall in Z-pinch driven fusion-fission hybrid energy reactor

作　　者：吴茜 祁建敏[1] 王真[1] Wu Xi;Qi Jianming;Wang Zhen(Instituteof Nuclear Physics and Chemistry,CAEP.P.O.Box 919 226,Mianyang 621999,China)

机构地区：[1]中国工程物理研究院核物理与化学研究所,四川绵阳621900

出　　处：《强激光与粒子束》2018年第9期138-141,共4页High Power Laser and Particle Beams

摘　　要：利用ANSYS程序对Z箍缩驱动聚变-裂变混合堆(Z-FFR)第一壁在瞬态热流加载下的热-力学响应进行了模拟计算,分析了第一壁温度、应力随时间和深度的分布。结果表明,周期性脉冲加载不会导致第一壁产生温度累积效应,第一壁温度峰值409℃,出现在钨层表面,钨层最大应力140 MPa,锆合金基底最大应力33 MPa。The simulation software ANSYS was used to calculate the thermal-mechanical response of the first wall in Zpinch driven fusion fission hybrid energy reactor under pulsed thermal flux, including distribution of temperature, stress and strain of the first wall materials along its depth direction. The results indicate that the periodic （10 s） transient pulse loading does not lead to the temperature accumulation in the first wall. The maximum temperature of the first wall appears on the surface of the tungsten coating. The maximum stress of the tungsten coating is 130 MPa. The maximum stress of the Zr alloy substrate is 33 MPa.

关 键 词：Z-FFR 第一壁 热-力学响应 有限元分析 

分 类 号：TL46[核科学技术—核技术及应用]