Development of reload safety-analysis methodology and code package: uncertainty analysis. Final report. [PWR; BWR]
This report presents the development of a statistical methodology proposed for use with the Electric Power Research Institute (EPRI) Reactor Analysis Support Package (RASP). The EPRI package is an integrated design methodology for use by utilities in reload core design, licensing, and operations support. Existing EPRI codes, including some currently under development, are major elements in the reload safety analysis methodology. As envisioned, the methodology will be applicable to both Pressurized Water Reactor (PWR) and Boiling Water Reactor (BWR) analyses. The current status of code development and availability has mandated that the scope of the present statistical effort be confined to a basic set of codes for the PWR analysis package. This consists of the neutronics (ARMP), systems analysis (RETRAN), and thermal-hydraulics (VIPRE) codes.
- Research Organization:
- Combustion Engineering, Inc., Windsor, CT (USA)
- OSTI ID:
- 5114969
- Report Number(s):
- EPRI-NP-2577; ON: DE82906458
- Country of Publication:
- United States
- Language:
- English
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