实验包层氚增殖区提氚气体换热研究  

Thermal analysis for gas containing tritium in tritium breeding blanket of the test blanket module

作　　者：周冰 冯勇进 王晓宇 武兴华 ZHOU Bing;FENG Yong-jin;WANG Xiao-yu;WU Xing-hua(Southwestern Institute of Physics,Chengdu 610041)

机构地区：[1]核工业西南物理研究院,成都610000

出　　处：《核聚变与等离子体物理》2018年第3期339-343,共5页Nuclear Fusion and Plasma Physics

摘　　要：描述了提氚气体(氦气)进入氚增值区后被正硅酸锂(Li4Si O4)小球加热的过程。通过现有实验包层(TBM)设计参数完成的提氚气体温升理论计算和三维数值模拟验证计算得到提氚气体经过球床时温度可以很快从20℃升到500℃。因此,在进行提氚系统设计优化时,中国设计的实验包层模块不需要增加额外设备对提氚气体进行预热。The process of the purge gas(helium) heated by the lithium silicon oxide(Li4SiO4) pebbles in the tritium breeding blanket is described. The theoretical calculation and three-dimensional numerical simulation of temperature rise have been carried out, based on the test blanket module(TBM) design detail. The results show that the temperature of the purge gas rises from 20℃ to 500℃ rapidly. So, it is no need to design the equipment to heat purge gas in the design optimization of tritium recovery system.

关 键 词：氚增殖区 聚变堆 氦气 数值模拟 

分 类 号：TL622[核科学技术—核技术及应用]