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Title: LAPUR5.2 Verification and User's Manual

Technical Report ·
DOI:https://doi.org/10.2172/777625· OSTI ID:777625

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.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
Nuclear Regulatory Commission (US)
DOE Contract Number:
AC05-96OR22464
OSTI ID:
777625
Report Number(s):
ORNL/TM-2000/340; TRN: US0102032
Resource Relation:
Other Information: PBD: 26 Feb 2001
Country of Publication:
United States
Language:
English