Actions for An improved numerical model for the investigation of thermal hydraulic phenomena with applications to LMR reactor components [electronic resource].

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An improved numerical model for the investigation of thermal hydraulic phenomena with applications to LMR reactor components [electronic resource].

Published
Rockville, Md. : U.S. Nuclear Regulatory Commission, 1992.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: (46 pages) : digital, PDF file
Additional Creators
Brookhaven National Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
A basic limited scope, fast-running computer model is presented for the solution of single phase two-dimensional transients in thermally coupled incompressible fluid flow problems. The governing equations and the two-equation transport model (k-ε) of turbulence are reduced to a set of linear algebraic equations in an implicit finite difference scheme, based on the control volume approach. These equations are solved iteratively in a line-by-line procedure using the tri-diagonal matrix algorithm. The numerical formulation and general calculational procedure are described in detail. The calculations show good agreement when compared with experimental data and other independent analyses.
Report Numbers
E 1.99:bnl-nureg-47747
E 1.99: conf-921110--11
conf-921110--11
bnl-nureg-47747
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Note
Published through SciTech Connect.
01/01/1992.
"bnl-nureg-47747"
" conf-921110--11"
"DE92018144"
Winter annual meeting of the American Society of Mechanical Engineers, Anaheim, CA (United States), 8-13 Nov 1992.
Chan, B.C.; Van Tuyle, G.J.; Kennett, R.J.
Funding Information
AC02-76CH00016
View MARC record | catkey: 14359370