Development and verification of NRC`s single-rod fuel performance codes FRAPCON-3 AND FRAPTRAN
- Pacific Northwest National Lab., Richland, WA (United States)
The FRAPCON and FRAP-T code series, developed in the 1970s and early 1980s, are used by the US Nuclear Regulatory Commission (NRC) to predict fuel performance during steady-state and transient power conditions, respectively. Both code series are now being updated by Pacific Northwest National Laboratory to improve their predictive capabilities at high burnup levels. The newest versions of the codes are called FRAPCON-3 and FRAPTRAN. The updates to fuel property and behavior models are focusing on providing best estimate predictions under steady-state and fast transient power conditions up to extended fuel burnups (> 55 GWd/MTU). Both codes will be assessed against a data base independent of the data base used for code benchmarking and an estimate of code predictive uncertainties will be made based on comparisons to the benchmark and independent data bases.
- Research Organization:
- Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, DC (United States); Brookhaven National Lab. (BNL), Upton, NY (United States)
- OSTI ID:
- 305921
- Report Number(s):
- NUREG/CP-0162-Vol.2; CONF-9710101-Vol.2; ON: TI98007504; TRN: IM9906%%173
- Resource Relation:
- Conference: 25. water reactor safety information meeting, Bethesda, MD (United States), 20-22 Oct 1997; Other Information: PBD: Mar 1998; Related Information: Is Part Of Twenty-fifth water reactor safety information meeting: Proceedings. Volume 2: Human reliability analysis and human performance evaluation; Technical issues related to rulemakings; Risk-informed, performance-based initiatives; High burn-up fuel research; Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)]; PB: 236 p.
- Country of Publication:
- United States
- Language:
- English
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