FRAPTRAN 1.4: A Computer Code for the Transient Analysis of Oxide Fuel Rods (NUREG/CR-7023, Volume 1, PNNL-19400, Volume 1)
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Publication Information
Manuscript Completed: August 2010
Date Published: March 2011
Prepared by:
K.J. Geelhood, W.G. Luscher, C.E. Beyer
J.M. Cuta
Pacific Northwest National Laboratory
P.O. Box 999
Richland, WA 99352
M.E. Flanagan, NRC Project Manager
NRC Job Code N6609
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington DC 20555-0001
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Abstract
The Fuel Rod Analysis Program Transient (FRAPTRAN) is a Fortran language computer code that calculates the transient performance of light-water reactor fuel rods during reactor transients and hypothetical accidents such as loss-of-coolant accidents, anticipated transients without scram, and reactivity-initiated accidents. FRAPTRAN calculates the temperature and deformation history of a fuel rod as a function of time-dependent fuel rod power and coolant boundary conditions. Although FRAPTRAN can be used in “standalone” mode, it is often used in conjunction with, or with input from, other codes.
The phenomena modeled by FRAPTRAN include a) heat conduction, b) heat transfer from cladding to coolant, c) elastic-plastic fuel and cladding deformation, d) cladding oxidation, e) fission gas release, and f) fuel rod gas pressure. FRAPTRAN is programmed for use on Windows-based computers but the source code may be compiled on any other computer with a Fortran-90 compiler.
Burnup-dependent parameters may be initialized from the FRAPCON-3 steady-state single rod fuel performance code.
This document describes FRAPTRAN 1.4, which is the latest version of FRAPTRAN.
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