Title: Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0.
Authors: He, Qingming; Zheng, Qi; Li, Jie; Huang, Zhanpeng; Huang, Jinlong; Qin, Shuai; Shu, Hanlin; Peng, Heyu; Yang, Xuran; Shen, Jingwen; Guo, Jiandi; Cao, Liangzhi; Wu, Hongchun
Abstract: NECP-MCX is a Monte-Carlo particle-transport code developed by the Nuclear Engineering Computational Physics (NECP) Lab. of Xi'an Jiaotong University in 2018. The first version of NECP-MCX is focused on addressing the challenge of deep-penetration radiation-shielding problems. In recent years, new capabilities of unstructured-mesh geometries, dose engine for Boron Neutron Capture Therapy (BNCT), neutron noise analysis, sensitivity analysis, depletion and activation calculation, simulation of randomly dispersed media, homogenization and gamma dose calculation based on point-kernel integral method are implemented in NECP-MCX V2.0. A user interface of NECP-MCX V2.0 is also under active development. This paper will introduce these new capabilities.
Subjects: BORON-neutron capture therapy; NUCLEAR engineering; COMPUTATIONAL physics; USER interfaces; SENSITIVITY analysis
Publication: EPJ Nuclear Sciences & Technologies, 2024, Vol 10, p1
ISSN: 2491-9292
Publication type: Academic Journal
DOI: 10.1051/epjn/2024014

Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0.

He, Qingming; Zheng, Qi; Li, Jie; Huang, Zhanpeng; Huang, Jinlong; Qin, Shuai; Shu, Hanlin; Peng, Heyu; Yang, Xuran; Shen, Jingwen; Guo, Jiandi; Cao, Liangzhi; Wu, Hongchun