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Tritium processing system for the ITER Li/V blanket test module [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy. Office of Energy Research, 1997.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
12 pages : digital, PDF file
Additional Creators
Argonne National Laboratory, United States. Department of Energy. Office of Energy Research, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate blanket concepts under a real fusion environment. To assure fuel self-sufficiency the tritium breeding, recovery and processing have to be demonstrated. The tritium produced in the blanket has to be processed to a purity which can be used for refueling. All these functions need to be accomplished so that the tritium system can be scaled to a commercial fusion power plant from a safety and reliability point of view. This paper summarizes the tritium processing steps, the size of the equipment, power requirements, space requirements, etc. for a self-cooled lithium blanket. This information is needed for the design and layout of the test blanket ancillary system and to assure that the ITER guidelines for remote handling of ancillary equipment can be met.
Report Numbers
E 1.99:anl/td/cp--93186
E 1.99: conf-970404--4
conf-970404--4
anl/td/cp--93186
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
04/01/1997.
"anl/td/cp--93186"
" conf-970404--4"
"DE97052882"
ISFNT-4: 4th international symposium on fusion nuclear technology, Tokyo (Japan), 6-11 Apr 1997.
Sze, D.K.; Abdou, M.A.; Waganer, L.M.; Hua, T.Q.; Dagher, M.A.
Funding Information
W-31109-ENG-38
View MARC record | catkey: 14741158