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Feasibility study of LiF-BeF/sub 2/ and chloride salts as blanket coolants for fusion power reactors

Author
Imamura, Y.
Published
United States : [publisher not identified], 1977.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1977.
Physical Description
microfiche : negative ; 11 x 15 cm

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Summary
The feasibility of using molten salts, in particular, nonberyllium-bearing chloride salts, as blanket coolants for Tokamak fusion reactors has been examined for the nucleonic and thermal/hydraulic aspects. It is concluded that the chloride salts, i.e., LiCl--KCl, LiCl--PbCl/sub 2/ and LiCl--SnCl/sub 2/, can be used as the blanket coolant for a static lithium metal blanket provided that large blanket thickness can be tolerated, along with the use of U-238 for neutron multiplication in the cases of LiCl--KCl or LiCl--SnCl/sub 2/ cooled blankets. However, to make the appraisal complete, the tritium recovery and corrosion problems must be examined extensively, based on data not yet at hand. As for LiF--BeF/sub 2/, it is observed that although the salt mixture can be used for a single fluid blanket with satisfactory nuclear performance, careful attention should be paid to the cooling capability.
Report Numbers
PPL-1380
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: EY-76-C-02-3073
OSTI Identifier 5420029
Research organization: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States).
Funding Information
Sponsored by US Energy Research and Development Administration (ERDA).
View MARC record | catkey: 47075313