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JUPITER-II Flibe Tritium/Chemistry and Safety Experimental Program

D. A. Petti, R. A. Anderl, G. R. Smolik, D.-K. Sze, T. Terai, S. Tanaka

Fusion Science and Technology / Volume 41 / Number 3P2 / May 2002 / Pages 807-811

Design and Model / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 /

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-BeF2 (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.

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