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LAPUR5.2 Verification and User's Manual [electronic resource].

Published
Rockville, Md. : U.S. Nuclear Regulatory Commission, 2001.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy
Physical Description
106 pages : digital, PDF file
Additional Creators
Oak Ridge National Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
This report documents a series of programming upgrades to increase the available number of thermal-hydraulic regions (i.e., channels) and other parameters in LAPUR. LAPUR, a computer program in FORTRAN, is a mathematical description of the core of a boiling water reactor. Its two linked modules, LAPURX and LAPURW, respectively solve the steady state governing equations for the coolant and fuel and the dynamic equations for the coolant, fuel, and neutron field in the frequency domain. General implementation descriptions are followed by a detailed description of input and output parameters of LAPURX and LAPURW. Sample inputs are included and stability benchmarks are noted. The original version of LAPUR was limited to seven channels; the current version, LAPUR 5.2, has been verified with up to 200 channels, each of which can have its own axial and radial power shape. Other significant parameter upgrade is the calculation of the transfer functions for up to 100 frequencies. All code dimensions are now parameterized and can be increased if necessary.
Report Numbers
E 1.99:ornl/tm-2000/340
ornl/tm-2000/340
Subject(s)
Note
Published through SciTech Connect.
02/26/2001.
"ornl/tm-2000/340"
Escriva, A.
Type of Report and Period Covered Note
Topical;
Funding Information
AC05-96OR22464
View MARC record | catkey: 23780525