Tritium release behavior from neutron-irradiated FLiNaBe mixed with titanium powder
Author:
Funder
National Institute for Fusion Science
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference9 articles.
1. First Operation of the Flinak/LiPb Twin Loop Orosh2i-2 with a 3T SC Magnet for R&D of Liquid Blanket for Fusion Reactor;Sagara;Fusion Sci. Technol.,2015
2. Helicalreactor design FFHR-d1 and c1 for steady-state DEMO;Sagara;Fusion Eng. Des.,2014
3. Hydrogen solubility in FLiNaK mixed with titanium powder;Yagi;Fusion Eng. Des.,2015
4. Hydrogen permeation through Flinabe fluoride molten salts for blanket candidates;Nishiumi;Fusion Eng. Des.,2016
5. Tritium release from neutron-irradiated Flibe purged out by Ar-H2 or Ar at controlled temperature;Edao;Fusion Sci. Technol.,2009
Cited by 2 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. Electromagnetic–thermal–mass transport triple hybrid model for energy-efficient hydrogen release from metal particles by induction heating;International Journal of Hydrogen Energy;2024-06
2. Tritium release behavior from neutron-irradiated FLiNaK mixed with Ti powder;Fusion Engineering and Design;2023-07
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