https://doi.org/10.1051/epjn/2024014
Regular Article
Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0
School of Nuclear Science and Technology, Xi’an Jiaotong University, No. 28 West Xianning Road, 710049, Xi’an, P.R. China
* e-mail: qingming_he@xjtu.edu.cn
Received:
13
June
2024
Received in final form:
21
August
2024
Accepted:
27
August
2024
Published online: 5 November 2024
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.
© Q. He et al., Published by EDP Sciences, 2024
This is an Open Access article distributed under the terms of the Creative Commons Attribution License (https://creativecommons.org/licenses/by/4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
