Jupiter-II Flibe Tritium/Chemistry and Safety Experimental Program

The second Japan/US Program on Irradiation Tests for Fusion Research (JUPITER-II) began on April 1, 2001. Part of the collaborative research centers on studies of the molten salt 2LiF-BeF 2 (also known as Flibe) for fusion applications. Flibe has been proposed as a self-cooled breeder in both magnet...

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Bibliographic Details
Published in:Fusion science and technology 2002-05, Vol.41 (3P2), p.807-811
Main Authors: Petti, D. A., Anderl, R. A., Smolik, G. R., Sze, D.-K., Terai, T., Tanaka, S.
Format: Article
Language:English
Subjects:
Breeder reactors
Breeding blankets
Cooling
Fusion reactions
Irradiation
Lithium compounds
Nuclear power plants
Salts
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Summary:The second Japan/US Program on Irradiation Tests for Fusion Research (JUPITER-II) began on April 1, 2001. Part of the collaborative research centers on studies of the molten salt 2LiF-BeF 2 (also known as Flibe) for fusion applications. Flibe has been proposed as a self-cooled breeder in both magnetic and inertial fusion power plant designs over the last twenty years. The key feasibility issues associated with the use of Flibe are the corrosion of structural material by the molten salt, tritium control in the molten salt blanket system, and safe handling practices and releases from Flibe during an accidental spill. An overview of the experimental program to address the key feasibility issues is presented.
ISSN:1536-1055
1943-7641
DOI:10.13182/FST02-A22696