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

doi:10.1051/epjn/2024014

EPJ Nuclear Sciences & Technologies (Jan 2024)

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

Affiliations

He Qingming: School of Nuclear Science and Technology, Xi’an Jiaotong University
Zheng Qi: School of Nuclear Science and Technology, Xi’an Jiaotong University
Li Jie: School of Nuclear Science and Technology, Xi’an Jiaotong University
Huang Zhanpeng: School of Nuclear Science and Technology, Xi’an Jiaotong University
Huang Jinlong: School of Nuclear Science and Technology, Xi’an Jiaotong University
Qin Shuai: School of Nuclear Science and Technology, Xi’an Jiaotong University
Shu Hanlin: School of Nuclear Science and Technology, Xi’an Jiaotong University
Peng Heyu: School of Nuclear Science and Technology, Xi’an Jiaotong University
Yang Xuran: School of Nuclear Science and Technology, Xi’an Jiaotong University
Shen Jingwen: School of Nuclear Science and Technology, Xi’an Jiaotong University
Guo Jiandi: School of Nuclear Science and Technology, Xi’an Jiaotong University
Cao Liangzhi: School of Nuclear Science and Technology, Xi’an Jiaotong University
Wu Hongchun: School of Nuclear Science and Technology, Xi’an Jiaotong University

DOI: https://doi.org/10.1051/epjn/2024014
Journal volume & issue: Vol. 10
p. 14

Abstract

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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.

Published in EPJ Nuclear Sciences & Technologies

ISSN: 2491-9292 (Online)
Publisher: EDP Sciences
Country of publisher: France
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.epj-n.org/

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