Introduction on tritium transport analysis model for HCCP breeding blanket system

被引:0
作者
Lee, Yonghee [1 ]
Ying, Alice [2 ]
Ahn, Mu-Young [1 ]
Jin, Hyung Gon [3 ]
Moon, Sungbo [1 ]
Kim, Myungho [1 ]
机构
[1] Korea Inst Fus Energy, Daejeon 34133, South Korea
[2] Univ Calif Los Angeles UCLA, Los Angeles, CA USA
[3] Korea Atom Energy Res Inst, Daejeon, South Korea
关键词
HCCP breeding blanket; Tritium transport model; PERMEATION; DESIGN;
D O I
10.1016/j.fusengdes.2024.114561
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
In the context of implementing the He-cooled breeding blanket system for a fusion reactor, several crucial aspects need consideration. Among these, the development of a tritium transport model plays a pivotal role in ensuring safety and effective design. Given that tritium release into the environment from the breeding blanket system poses a radioactive risk, accurate calculation and prediction area essential to prevent potential incidents in a fusion reactor. To address this challenge, a collaborative effort between the Korea Institute of Fusion Energy (KFE) and the University of California, Los Angeles (UCLA) resulted in the creation of THETA-FR (Tritium/ Hydrogen Enhanced dynamic Transport Analysis Tool for Fusion Reactor). THETA-FR is an integrated analysis tool that combines Matlab Simulink and COMSOL Multiphysics. Its purpose is to model and predict the dynamic transport phenomena of H isotopes (H/D/T) within the breeding blanket system. Specifically, THETA-FR focuses on transient tritium retention, permeation, and release amounts from the breeding blanket system into the environment. In this paper, we introduce the integrated system and components of THETA-FR, shedding light on various tritium behaviors within the HCCP breeding blanket FW/BU component. By leveraging THETA-FR, researchers and engineers can make informed decisions regarding tritium control and safety in fusion reactors.
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页数:11
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