VALIDATION OF MVP CODE WITH HTC CRITICAL EXPERIMENTS

摘要

In the 1980s, a series of the Haut Taux de Combustion (HTC) critical experiments was conducted at the Apparatus B experimental facility in Valduc with the support of the IRSN and AREVA NC. Four series of experiments were designed to assess profit associated with acti-nide-only burn-up credit in the criticality safety analysis for fuel handling (Phases 1 and 2), pool storage (Phase 3) and spent fuel cask (Phase 4) conditions. The HTC rods, specifically fabricated for the experiments, were designed to simulate a typical pressurized water reactor uranium oxide spent fuel. In order to validate the MVP-2.0 code and relatively new nuclear data libraries for the criticality safety analysis, the HTC critical experiments were analyzed using the MVP-2.0 code with JENDL-4.0, ENDF/B-VII.l or JEFF-3.2. The effective neutron multiplication factor k_(eff) values were obtained through analyses of all phases of the HTC experiments. It was shown that averaged values of k_(eff) using JENDL-4.0 and ENDF/B-VII. 1 were in good agreement with experimental results for all the phases, while those using JEFF-3.2 showed slight underestimation.