Speaker
Description
Yonghee Lee1, Alice Ying2, Mu-Young Ahn1, Hyung Gon Jin3, Sungbo Moon1, Myungho Kim1
1Korea Institute of Fusion Energy, Daejeon, Korea
2University of California, Los Angeles (UCLA), LA, USA
3Korea Atomic Energy Research Institute, Daejeon, Korea
To implement a tritium breeding blanket in a fusion reactor, extensive research and efforts are required. Among these, the development of a tritium transport analysis model is critical for establishing both the safety and design criteria of the tritium breeding blanket. While the tritium is transported from the breeding blanket to the tritium facility, some of tritium may be released into external environment, which can be a serious risk to the working environment. Accordingly, to ensure operational safety of the breeding blanket system, the Korea Institute of Fusion Energy (KFE) has started to develop the tritium transport analysis platform, THETA-FR (Tritium/Hydrogen Enhanced dynamic Transport Analysis platform for Fusion Reactor), in collaboration with UCLA. THETA-FR is based on COMSOL Multiphysics and MATLAB Simulink, and the development of the components and the integrated system of THETA-FR has been completed recently. THETA-FR simultaneously performs dynamic heat transfer analysis and H isotope diffusion analysis at the sub-system level for each component of the breeding blanket system and integrates the results at the system level to expect the comprehensive tritium behavior. Through THETA-FR, it is expected that the effective design guidelines for tritium management and safety in the breeding blanket system can be established.
