TY - JOUR
T1 - Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0
AU - He, Qingming
AU - Zheng, Qi
AU - Li, Jie
AU - Huang, Zhanpeng
AU - Huang, Jinlong
AU - Qin, Shuai
AU - Shu, Hanlin
AU - Peng, Heyu
AU - Yang, Xuran
AU - Shen, Jingwen
AU - Guo, Jiandi
AU - Cao, Liangzhi
AU - Wu, Hongchun
N1 - Publisher Copyright:
© Q. He et al., Published by EDP Sciences, 2024.
PY - 2024
Y1 - 2024
N2 - 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 NECPMCX 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.
AB - 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 NECPMCX 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.
UR - https://www.scopus.com/pages/publications/105023104855
U2 - 10.1051/epjn/2024014
DO - 10.1051/epjn/2024014
M3 - 文章
AN - SCOPUS:105023104855
SN - 2491-9292
VL - 10
JO - EPJ Nuclear Sciences and Technologies
JF - EPJ Nuclear Sciences and Technologies
M1 - 14
ER -