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Heat transfer effects in vertically emplaced high level nuclear waste container [electronic resource].

Published:
Washington, D.C. : United States. Dept. of Energy, 1994.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:
7 pages : digital, PDF file
Additional Creators:
United States. Department of Energy and United States. Department of Energy. Office of Scientific and Technical Information
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Summary:
Modeling free convection heat transfer in an cylindrical annular enclosure is still an active area of research and an important problem to be addressed in the high level nuclear waste repository. For the vertically emplaced waste container, the air gap which is between the container shell and the rock borehole, have an important role of dissipating heat to surrounding rack. These waste containers are vertically emplaced in the borehole 300 meters below ground, and in a horizontal grid of 30 × 8 meters apart. The borehole will be capped after the container emplacement. The expected initial heat generated is between 3--4.74 kW per container depending on the type of waste. The goal of this study is to use a computer simulation model to find the borehole wall, air-gap and the container outer wall temperature distributions.
Report Numbers:
E 1.99:conf-940553--58
conf-940553--58
Subject(s):
Other Subject(s):
Note:
Published through SciTech Connect.
05/01/1994.
"conf-940553--58"
"DE94012151"
"DB0102100/DB0511010"
International high-level radioactive waste management conference,Las Vegas, NV (United States),22-26 May 1994.
Moujaes, S.F.; Lei, Y.M.
Nevada Univ., Las Vegas, NV (United States)
Funding Information:
FC08-90NV10872
View MARC record | catkey: 14414885