Benchmark of cosRMC with CFETR fusion neutronics model

摘要

cosRMC is a three dimensional Monte Carlo code for coupled neutron and photon transport simulation, it is jointly developed for fission reactor by State Power Investment Corporation Research Institute of China, Tsinghua University and North China Electric Power University. In order to evaluate its feasibility and accuracy in fusion neutronics analysis, a preliminary benchmark is conducted on cosRMC using CFETR fusion neutronics model with the WCCB blanket module. The tritium breeding ratio (TBR), nuclear heating (NH) and neutron wall loading (NWL) are calculated by cosRMC, and the results are compared with those calculated by MCNP with the same nuclear data library FENDL-2.1. Preliminary comparison results show that a very good consistency is obtained between the two Monte Carlo codes: the relative differences of calculated results are mostly within 1% and the statistical errors are within the statistical uncertainty of the MC method.