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

doi:10.16568/j.0254-6086.201803016

NUCLEAR FUSION AND PLASMA PHYSICS ›› 2018, Vol. 2 ›› Issue (3): 339-343.DOI: 10.16568/j.0254-6086.201803016

• Nuclear Fusion Engineering and Technology • Previous Articles Next Articles

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

ZHOU Bing, FENG Yong-jin, WANG Xiao-yu, WU Xin-hua

(Southwestern Institute of Physics, Chengdu 610041)

Received:2017-06-28 Revised:2018-04-08 Online:2018-09-15 Published:2018-09-14

实验包层氚增殖区提氚气体换热研究

周冰，冯勇进，王晓宇，武兴华

(核工业西南物理研究院，成都 610000)

作者简介:周冰(1981-)，男，四川内江人，工程师，从事热工水力与数值模拟工作。

Abstract

Abstract:

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.

Key words: 氚增殖区, 聚变堆, 氦气, 数值模拟

摘要：

描述了提氚气体(氦气)进入氚增值区后被正硅酸锂(Li4SiO4)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。

关键词: 氚增殖区, 聚变堆, 氦气, 数值模拟

CLC Number:

TL62+2

ZHOU Bing, FENG Yong-jin, WANG Xiao-yu, WU Xin-hua. Thermal analysis for gas containing tritium in tritium breeding blanket of the test blanket module[J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2018, 2(3): 339-343.

周冰，冯勇进，王晓宇，武兴华. 实验包层氚增殖区提氚气体换热研究[J]. 核聚变与等离子体物理, 2018, 2(3): 339-343.

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

实验包层氚增殖区提氚气体换热研究

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