FRAPTRAN Fuel Rod Code and its Coupled Transient Analysis with the GENFLO Thermal-Hydraulic Code

May 1, 2002

Conference Paper

FRAPTRAN Fuel Rod Code and its Coupled Transient Analysis with the GENFLO Thermal-Hydraulic Code

Abstract

The FRAPTRAN computer code has been developed for the U.S. Nuclear Regulatory Commission (NRC) to calculate fuel behavior during power and/or cooling transients at burnup levels up to 65 MWd/kgM. FRAPTRAN has now been assessed and peer reviewed. STUK/VTT have coupled GENFLO to FRAPTRAN for calculations with improved coolant boundary conditions and prepared example calculations to show the effect of improving the coolant boundary conditions.

Revised: August 26, 2003 | Published: May 1, 2002

Citation

Valtonen K., A. Hamalainen, and M.E. Cunningham. 2002. FRAPTRAN Fuel Rod Code and its Coupled Transient Analysis with the GENFLO Thermal-Hydraulic Code. In Proceedings of the Twenty-Ninth Nuclear Safety Research Conference, NUREG/CP-0176, 381-396. Washington, District Of Columbia:Nuclear Regulatory Commission. PNNL-SA-35742.