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Tritium permeation in fusion reactors [electronic resource] : INTOR

Published:
Albuquerque, N.M. : Sandia National Laboratories, 1981.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:
Pages: 13 : digital, PDF file
Additional Creators:
Sandia National Laboratories and United States. Department of Energy. Office of Scientific and Technical Information
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Summary:
Tritium permeation through the first wall of advanced fusion reactors is examined. A fraction of the D-T which bombards the first wall as charge exchange neutral particles will permeate through the first wall and enter the coolant. Calculations of the steady state permeation rate for the US INTOR Tokamak design result in values of less than or equal to 0.002 grams of tritium per day under the most favorable conditions. For unfavorable surface conditions the rate is greater than or equal to 0.1 g/day. The magnitude of these permeation rates is critically dependent on the temperatures and surface conditions of the wall. The introduction of permeation barriers at the wall-coolant interface can significantly reduce permeation rates and hence may be desirable for reactor applications.
Report Numbers:
E 1.99:sand-81-8264
sand-81-8264
Subject(s):
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Note:
Published through SciTech Connect.
12/01/1981.
"sand-81-8264"
"DE82011189"
Wilson, K.L.; Bauer, W.; Baskes, M.I.; Swansiger, W.A.; Kerst, R.A.
Funding Information:
AC04-76DP00789
View MARC record | catkey: 14753823