2019•The Proceedings of the International Conference on Nuclear Engineering (ICONE)Open access
APPLICATION OF MONTE CARLO CODE COSRMC IN FUSION NEUTRONICS
Shichang Liu, Qin YAO, Yiman YAN, Hua Du, Yeshuai Sun, Yu Zheng, Songlin LIU, Yixue Chen
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Abstract
cosRMC is a continuous-energy reactor Monte Carlo neutron and photon transport code. As one of new generation Monte Carlo codes, cosRMC has been successfully applied to fission reactor modeling and simulations, such as pressurized water reactor, high temperature gas cooled reactor and so on. In this paper, new capacities were developed in cosRMC for the simulation of fusion reactor, including the handling of high order complex geometry, fusion related parameters tally, variance reduction technique and so on. cosRMC was applied to the simulation of Chinese Fusion Engineering Testing Reactor (CFETR) and the calculation results were compared with reference code. The results show that key fusion related parameters including Tritium Breeding Ratio (TBR), Neutron Wall Loading and nuclear heat agree well with that of reference code. Moreover, with the global variance reduction technique, the global flux of the entire fusion building can be achieved. cosRMC was proved to be accurate for both fission and fusion neutronics calculation, and it will be an effective tool for simulation of fusion reactor such as CFETR.