Tritium transport analysis for WCCB blanket of CFETR based on COMSOL

被引:7
|
作者
Zhao, Xueli [1 ,2 ]
Zhang, Bing [1 ,2 ]
Chen, Lei [1 ]
Huang, Kai [1 ]
Liu, Songlin [1 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
[2] Univ Sci & Technol China, Hefei 230037, Anhui, Peoples R China
关键词
WCCB blanket; Tritium permeation; Tritium inventory; Tritium release; COMSOL; PERMEATION; RETENTION; RELEASE; MODEL; F82H;
D O I
10.1016/j.fusengdes.2019.01.044
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
As for the fusion reactor, tritium has received widely attention due to its self-sufficiency and its influence on the safe operation of the fusion reactor. As a result, quantitative analysis of tritium diffusion, inventory, permeation in the blanket is crucial to the design of tritium fuel circulating system and safety issue. In this study, a two-dimensional model for tritium transport in water cooled ceramic breeder (WCCB) blanket is created, and finite element software COMSOL is used to simulate the tritium transport process. The amount of tritium inventory, the tritium permeation into the coolant, the tritium taken by purge gas and the tritium release are calculated. Besides, the concentration profile of tritium and temperature profile in the blanket are given as well as the sensitivity analysis about the velocity of purge gas is conducted which can offer a reference for the design of tritium extraction system.
引用
收藏
页码:1 / 10
页数:10
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