Development of Reload Safety Analysis Methodology and Code Package Uncertainty Analysis: Amplification of Statistical Bases. Final Report

摘要

NP-2577 presented the development of a statistical methodology proposed for use with Electric Power Research Institute (EPRI) Reactor Analysis Support Package (RASP). A subset of RASP, consisting of neutronics (ARMP), systems analysis (RETRAN), and thermal-hydraulics (VIPRE) codes, was considered in Pressurized Water Reactor (PWR) applications. This report supplements NP-2577 in amplifying the discussion of the statistical techniques suggested for use with RASP. In addition, further details of the classification of the uncertainty components are presented. Recommendations are made for future prototypical computations using RASP, which involve an effort expanded to include monitoring and protection system setpoint analyses. (ERA citation 08:014734)