LAPUR5.2 Verification and User's Manual

Technical Report · Mon Feb 26 04:00:00 EST 2001

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

Escriva, A ^[1]

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1. ORNL

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., TN (US)
• Sponsoring Organization: Nuclear Regulatory Commission (US)
• DOE Contract Number: AC05-96OR22464
• OSTI ID: 777625
• Report Number(s): ORNL/TM-2000/340
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
BWR TYPE REACTORS
FUEL-COOLANT INTERACTIONS
L CODES
RADIATION EFFECTS
REACTOR CORES
STABILITY
TRANSFER FUNCTIONS
VERIFICATION