The neutron-photon-coupling analysis of the tritium-breeding blanket in CFETR by NECP-MCX

• Published in: Fusion engineering and design Vol. 172; p. 112747
• Main Authors: Li, Jie, Wu, Hongchun, He, Qingming, Shen, Wei, Zheng, Qi, Cao, Liangzhi, Cao, Qixiang, Qu, Shen
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 01.11.2021; Elsevier Science Ltd
• Subjects: CFETR; Coupling; Engineering test reactors; Fusion reactor; Monte Carlo method; NECP-MCX; Neutron-photon transport; Nuclear engineering; Nuclear reactor components; Nuclear reactors; Photons; Tritium; Neutron-photon transport; Monte Carlo method; CFETR; NECP-MCX; Fusion reactor
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2021.112747

•The development of neutron-photon-coupling transport in a newly developed Monte Carlo code NECP-MCX.•The neutron-photon-coupling analysis is performed for CFETR.•NECP-MCX is capable to obtain more reliable results of photon kerma than MCNP. 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.