Abstract
The design of Chinese Fusion Engineering Test Reactor (CFETR) is being carried out. The neutronics analysis of the tritium-breeding blankets in CFETR is one of the essential tasks, and raises requirements for the neutronics-analysis codes such as the ability of simulating the neutron-photon-coupling transport and the ability of obtaining the accurate energy deposition of neutrons and photons. NECP-MCX is a hybrid Monte-Carlo-deterministic code newly developed by the Nuclear Engineering Computational Physics (NECP) Lab at Xi'an Jiaotong University. In order to meet the requirements raised by CFETR, the neutron-photon-coupling transport and other related functionalities are developed in NECP-MCX. The code-to-code verification shows that the results of NECP-MCX agree well with those of other codes. The application of NECP-MCX for the neutron-photon-coupling analysis of the tritium-breeding blankets in CFETR shows that NECP-MCX can obtain more reliable results of photon kerma than MCNP.
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