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LAPUR 6.0 Manual (NUREG/CR-6958)

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Publication Information

Manuscript Completed: December 2007
Date Published: October 2008

Prepared by:
Alberto Escrivá
José Luis Munoz Cobo
José Melara San Roman
Manuel Albendea Darriba
José March-Leuba

Oak Ridge National Laboratory
P.O. Box 2008
Oak Ridge, TN 37831

T. Huang, NRC Project Manager

NRC Job Code J3319

Office of Nuclear Reactor Regulation
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Availability Notice

Abstract

This report documents a series of programming upgrades to Version 6.0 of the LAPUR code. 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. The main upgrade in LAPUR 6 is the ability to model part-length fuel rods and fuel spacers explicitly. 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.

Page Last Reviewed/Updated Wednesday, March 24, 2021