Validation of an MCNP4B whole-reactor model for LWR-PROTEUS using ENDF/B-V, ENDF/ B-VI and JEF-2.2 cross-section libraries

摘要

A detailed three-dimensional, continuous-energy MCNP4B model of the LWR-PROTEUS critical facility has been developed for the analysis of whole-reactor characteristics using ENDF/B-V, ENDF/B-VI and JEF-2.2 cross-section sets. The model has been applied to the Determination of the critical loading, as well as the evaluation of reactivity worths for safety/ Shutdown rods, control rods, and individual driver-region fuel rods.