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

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

doi:10.1051/epjn/2024014

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

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

School of Energy and Power Engineering

Xi'an Jiaotong University

Research output: Contribution to journal › Article › peer-review

5 Scopus citations

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 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.

Original language	English
Article number	14
Journal	EPJ Nuclear Sciences and Technologies
Volume	10
DOIs	https://doi.org/10.1051/epjn/2024014
State	Published - 2024

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

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 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.",

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

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year = "2024",

doi = "10.1051/epjn/2024014",

language = "英语",

volume = "10",

journal = "EPJ Nuclear Sciences and Technologies",

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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

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 -

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

Abstract

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