Diffusion Coefficient of Tritium Through Molten Salt Flibe and Rate of Tritium Leak from Fusion Reactor System
Journal Article
·
· Fusion Science and Technology
OSTI ID:20854235
- Kyushu University (Japan)
- Idaho National Engineering and Environmental Laboratory (United States)
- National Institute for Fusion Science (Japan)
Diffusion coefficients of hydrogen isotopes in Flibe were correlated with making reference to previous relating data of F{sup -} ion self-diffusivity and Flibe viscosity and so on. Rates of tritium permeation through structural materials in a fusion reactor system with Flibe blanket were estimated comparatively under conditions with or without a Flibe permeation barrier. A way to lower the tritium leak rate below a level regulated by law was proposed, and its effectiveness was discussed.
- OSTI ID:
- 20854235
- Journal Information:
- Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 1 Vol. 48; ISSN 1536-1055
- Country of Publication:
- United States
- Language:
- English
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