Neutronics benchmarks for the utilization of mixed oxide fuel in water reactors

摘要

This paper presents results of criticality calculations performed for three sets of benhcmark problems conducted with four computer code systems. The problems presented in this paper include both experimental and computational benchmarks. These calculations were performed for the Amarillo Resource Center for Plutonium (ANRCP) in conjunction with the Oak Ridge National Laboratory (ORNL). Each of the following sections contains an abbreviated problem statement, a brief description of the calculational methodology, and primary results. MCNP-4A with ENDF/B-VI is used for the Monte Carlo calculations. WIMSD4-m/TWODANT, WIMSDR-m/DIF3D, and CASMO-3 are used for different parts of the deterministic calculations. Due to space constraints, the descriptions given below are quite brief. Please contact the authors if further information is desired.