Development and validation of a new multigroup Monte Carlo Criticality Calculations (MC3) code

摘要

MC3 is a new multigroup Monte Carlo criticality calculations code based on the standard power method that is currently under development at the Shahid Beheshti University (SBU). It is capable of simulating 3D models based on combinatorial geometry with first or second-order surfaces, and macro bodies capability. The code also merits a multilevel lattice-universe based geometry model to simulate rectangular, rotated rectangular, standard hexagonal, or rotated standard hexagonal repeated structures which are frequently applicable in nuclear reactor analysis. In this code, multigroup cross sections with Data Table Format are used to simulate neutron physics and utilizes a new internal converter for taking into account anisotropy of scattering (described by Legendre polynomials) into a Monte Carlo algorithm. For fast scoring volumetric parameters a new coarse-fine mesh tally is embedded in the MD code.