PERFORMANCE OF ON-THE-FLY CROSS SECTIONS PROCESSING IN MONTE CARLO SIMULATION CODE

MCS is an advanced Monte Carlo Simulation code being developed by Ulsan National Institute of Science and Technology (UNIST) for neutron transport and reactor physics analysis. It has a complete capability of On-The-Fly processing cross sections with temperatures dependence, which covers the whole incidental energy range, i.e. thermal, resolved resonance, as well as unresolved resonance range. With validation of single fuel rod test and whore core BEAVRS benchmark, this paper presents the performance of the key algorithms successfully implemented in MCS code to treat with cross sections during neutron transport, including Improved SIGMA1 kernel, Optimized S(a,b) interpolation and probability tables interpolation scheme