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Recent work on sodium-cooled reactor purification systems [electronic resource].

Published
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1978.
Physical Description
Pages: 46 : digital, PDF file
Additional Creators
Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
Fast Flux Test Facility (FFTF) cold traps, including the Reactor Primary Cold Trap, the Reactor Secondary Cold Trap and the Closed Loop Cold Trap were fabricated and their thermal performances measured on sodium test systems. The cold traps all met reactor requirements after necessary economizer modifications. Mercury tests were performed to study the effect of woven wire packing on the flow of a liquid metal adjacent to a heated vertical wall as occurs in the cold trap crystallizer. The mesh was observed to alter the velocity distribution in the natural convection flow region. Cold trapping experiments have been done to determine the interaction of hydrogen and tritium isotopes during precipitation. It was determined that the hydrogen removal rate is of primary importance in tritium removal from sodium. Isotopic exchange plays a negligible role in cold trapping tritium. A one-dimensional computer model has been developed to predict hydride and oxide precipitation patterns. Experiments have been done using an essentially one-dimensional (long, thin) tube to compare results with the model.
Report Numbers
E 1.99:hedl-sa-1446
E 1.99: conf-780677-2
conf-780677-2
hedl-sa-1446
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
02/01/1978.
"hedl-sa-1446"
" conf-780677-2"
U.S. Japanese information exchange, Richland, WA, USA, Jun 1978.
Bloom, G.R.; McPheeters, C.C.
Hanford Engineering Development Lab., Richland, WA (USA)
Funding Information
EY-76-C-14-2170
View MARC record | catkey: 14804018