Analysis on Tritium Management in FLiBe Blanket for LHD-Type Helical Reactor FFHR2

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概要

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• In FFHR2 (LHD-type helical reactor) design, FLiBe has been selected as a self-cooling tritium breeder for low reactivity with oxygen and water and lower conductivity. Considering the fugacity of the tritium, particular care and adequate mitigation measures should be applied for the effectively extracting tritium from breeder and controlling the tritium release to the environment. In this paper, a tritium analysis model of the FLiBe blanket system was developed and the preliminary analysis on tritium permeation and extraction for FLiBe blanket system were done. The results of the analysis showed that it was reasonable to select W alloy as heat exchanger (HX) material, the proportion of FLiBe flow in tritium recover system (TRS) was 0.2, the efficiency of TRS was 0.85 and tritium permeation reduction factor (TPRF) was 20 in blanket etc.. In addition, further R&D efforts were required for FFHR2 tritium system to guarantee the tritium self-sufficient and safety, for example reasonable quality of tritium permeation barriers on blanket, requirement for the TRS and fabrication technology of the heat exchanger etc..

• 社団法人 プラズマ・核融合学会の論文

著者

• Song Yong

  Institute Of Functional Biomolecules State Key Laboratory Of Pharmaceutical Biotechnology Nanjing Un

• SAGARA Akio

  Reactor Engineering Research Center, National Institute of Fusion Sciences

• MUROGA Takeo

  Reactor Engineering Research Center, National Institute of Fusion Sciences

• HUANG Qunying

  Institute of Plasma Physics, Chinese Academy of Sciences

• NI Muyi

  School of Nuclear Science and Technology, University of Science and Technology of China

• WU Yican

  Institute of Plasma Physics, Chinese Academy of Sciences

• SONG Yong

  Institute of Plasma Physics, Chinese Academy of Sciences

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• Analysis on Tritium Management in FLiBe Blanket for LHD-Type Helical Reactor FFHR2

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