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Home NRC Library Document Collections NUREG-Series Publications Publications Prepared by NRC Contractors FRAPTRAN: NRC's Computer Code (NUREG/CR-6739)

FRAPTRAN:  A Computer Code for the Transient Analysis of Oxide Fuel Rods (NUREG/CR-6739, Volume 1)

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Publication Information

Manuscript Completed: August 2001
Date Published: August 2001

Prepared by:
M.E. Cunningham, C.E. Beyer, F.E. Panisko, P.G. Medvedev, PNNL
G.A. Bema, GABC

Pacific Northwest National Laboratory
Richland, WA 99352

Subcontractor:
G.A. Berna Consulting
2060 Sequoia Drive
Idaho Falls, ID 83404

H. Scott, NRC Project Manager

Prepared for:
Division of Systems Analysis and Regulatory Effectiveness
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

NRC Job Code W6200

Availability Notice

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 power and coolant transients for 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 function of time-dependent fuel rod power and coolant boundary conditions. FRAPTRAN is intended to be used as a "stand alone" code. 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, and e) fuel rod gas pressure. FRAPTRAN was developed from the FRAP-T6 code and incorporates burnup-dependent parameters and corrects errors. Burnup dependent parameters may be initialized from the FRAPCON-3 steady-state single rod fuel performance code.

Page Last Reviewed/Updated Wednesday, March 24, 2021