Fusion Science and Technology / Volume 8 / Number 2P2 / September 1985 / Pages 2213-2216
Blanket and Process Engineering / Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) / dx.doi.org/10.13182/FST85-A24611
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Leakage of tritium resulting from permeation through surfaces such as those of the heat exchanger is a problem of special concern to fusion reactors. In this paper permeation rates are evaluated and their impact on the design of a fusion power system is assessed.