Analysis of coolability of the control rods of a Savannah River Site production reactor with loss of normal forced convection cooling [electronic resource].

Published: Washington, D.C. : United States. Dept. of Energy, 1992.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description: Pages: (16 pages) : digital, PDF file
Additional Creators: Westinghouse Savannah River Company, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary

An analytical study of the coolability of the control rods in the Savannah River Site (SRS) K-Production Reactor under conditions of loss of normal forced convection cooling has been performed. The study was performed as part of the overall safety analysis of the reactor supporting its restart. The analysis addresses the buoyancy-driven flow over the control rods that occurs when forced cooling is lost, and the limit of critical heat flux that sets the acceptance criteria for the study. The objective of the study is to demonstrate that the control rods will remain cooled at powers representative of those anticipated for restart of the reactor. The study accomplishes this objective with a very tractable simplified analysis for the modest restart power. In addition, a best-estimate calculation is performed, and the results are compared to results from sub-scale scoping experiments. 5 refs.

Report Numbers

E 1.99:wsrc-ms-92-129
E 1.99: conf-920903--5
conf-920903--5
wsrc-ms-92-129

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Note

Published through SciTech Connect.
01/01/1992.
"wsrc-ms-92-129"
" conf-920903--5"
"DE92013219"
International topical meeting on reactor thermal hydraulics: towards the next generation of nuclear power plants, Salt Lake City, UT (United States), 20-24 Sep 1992.
Smith, D.C.; Easterling, T.C.; Amos, C.N.; Hightower, N.T.

Funding Information

AC09-89SR18035

View MARC record | catkey: 14366356