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Lithium mass transport in ceramic breeder materials [electronic resource].

Published:
Washington, D.C. : United States. Office of the Assistant Secretary for Nuclear Energy, 1990.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:
Pages: (5 pages) : digital, PDF file
Additional Creators:
Argonne National Laboratory, United States. Office of the Assistant Secretary for Nuclear Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary:
The objective of this activity is to measure the lithium vaporization from lithium oxide breeder material under differing temperature and moisture partial pressure conditions. Lithium ceramics are being investigated for use as tritium breeding materials. The lithium is readily converted to tritium after reacting with a neutron. With the addition of 1000 ppM H₂ to the He purge gas, the bred tritium is readily recovered from the blanket as HT and HTO above 400°C. Within the solid, tritium may also be found as LiOT which may transport lithium to cooler parts of the blanket. The pressure of LiOT(g), HTO(g), or T₂O(g) above Li₂O(s) is the same as that for reactions involving hydrogen. In our experiments we were limited to the use of hydrogen. The purpose of this work is to investigate the transport of LiOH(g) from the blanket material. 8 refs., 1 fig., 3 tabs.
Report Numbers:
E 1.99:conf-901007-40
conf-901007-40
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Note:
Published through SciTech Connect.
01/01/1990.
"conf-901007-40"
"DE91006449"
9. topical meeting on technology of fusion energy, Oak Brook, IL (USA), 7-11 Oct 1990.
Johnson, C.E.; Blackburn, P.E.
Funding Information:
W-31109-ENG-38
View MARC record | catkey: 14754187