DETAILED VIPRE CORE MODELS FROM SIMULATE-3K

摘要

In depth analysis of Reactivity Initiated Accidents (RIA) and plant transients in Pressurized Water Reactors (PWR), requires the integration of many different analytical tools. One such tool, the 3D nodal transient code SIMULATE-3K (S3K) has been coupled with the system codes RELAP5-3D, RELAP5-Mod3.3 and TRACE, to provide a best-estimate coupled code system for performing plant transient calculations with reactivity feedback from a detailed core model. More recently, S3K has been coupled with the fuel performance code ENIGMA. The combination of these two codes provides a powerful analytical tool for the analysis of RIA. In line with these previous developments, one would like to be able to have an in-depth analysis of the fuel assemblies Thermal-Hydraulic (TH) performance during RIA and plant transients. The first step in this direction is the interface between S3K and VIPRE. The purpose of this paper is to describe the status of the S3K/VIPRE interface and to show its application to a Rod Ejection Accident (REA) scenario.