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          NRC Library  Document Collections  NUREG-Series Publications  Publications Prepared by NRC Contractors  FRAPCON-3.4 and FRAPCON-3.5 (NUREG/CR-7022)FRAPCON-3.5: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup (NUREG/CR-7022, Volume 1, Revision 1)

On this page: Publication Information AbstractDownload complete document NUREG/CR-7022, Volume 1, Revision 1 (PDF - 2.17 MB)Publication Information **Manuscript Completed:** May 2014**Date Published:** October 2014 **Prepared by:** K. J. Geelhood and W. G. Luscher Pacific Northwest National Laboratory Richland, WA 99352 P. Raynaud, NRC Project Manager NRC Job Code V6197 Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington DC 20555-0001 Availability Notice Abstract FRAPCON-3 is a Fortran 90 computer code that calculates the steady-state response of light-water reactor fuel rods during long-term burnup. The code calculates the temperature, pressure, and deformation of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena modeled by the code include: 1) heat conduction through the fuel and cladding to the coolant; 2) cladding elastic and plastic deformation; 3) fuel-cladding mechanical interaction; 4) fission gas release from the fuel and rod internal pressure; and 5) cladding oxidation. The code contains necessary material properties, water properties, and heat-transfer correlations. FRAPCON-3 is programmed for use on Windows-based computers, but the source code may be compiled on any computer with a Fortran 90 compiler. The FRAPCON-3 code is designed to perform steady-state fuel rod calculations and to generate initial conditions for transient fuel rod analysis by the FRAPTRAN computer code. This document describes FRAPCON-3.5, which is the latest version of FRAPCON-3, released May, 2014. 
      
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