Abstract
Monte Carlo transport codes are extensively used in neutronic analysis, especially in criticality safety analysis and shielding analysis. Super Monte Carlo Simulation Program for Nuclear and Radiation Process (SuperMC) is a CAD based Monte Carlo program for integrated simulation of nuclear systems. The aim of this paper was to show the capability of SuperMC on criticality calculation with different models. In this study 119 representative benchmarks from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP) were used for validating the code. All the benchmark models and input files were built and completed by employing the models’ conversion and construction function of SuperMC. The results showed that there was a good agreement between SuperMC and experimental data, and the discrepancies were mainly included in the statistical uncertainty.
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