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Title: The chemistry of molten Li sub 2 BeF sub 4

Conference · · Transactions of the American Nuclear Society; (USA)
OSTI ID:6764867

Renewed interest in molten Li{sub 2}BeF{sub 4} as a tritium breeding blanket suggests that a review of this solvent system is appropriate. Previous examination of this use for Li{sub 2}BeF{sub 4} was based on the data obtained at Oak Ridge National Laboratory during the molten salt breeder (fission) reactor program in the 1960s and 1970s. In discussing the thermochemistry, it is clear that T{sub 2} will be the major tritium species recovered from the blanket unless HF-resistant alloys (Hastelloy) or special coatings are used. Although T{sub 2} recovery systems have been examined, hydrogen permeation of metals at 1000 K complicates the problem. Water will not react with Li{sub 2}BeF{sub 4} to produce H{sub 2} but it does react to produce HF and BeO. 8 refs., 2 tabs.

OSTI ID:
6764867
Report Number(s):
CONF-860610-Summs.; CODEN: TANSA; TRN: 90-022125
Journal Information:
Transactions of the American Nuclear Society; (USA), Vol. 52; Conference: American Nuclear Society annual meeting, Reno, NV (USA), 15-20 Jun 1986; ISSN 0003-018X
Country of Publication:
United States
Language:
English