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

被引：1

作者：

He, Qingming ^{[1
]}

Zheng, Qi ^{[1
]}

Li, Jie ^{[1
]}

Huang, Zhanpeng ^{[1
]}

Huang, Jinlong ^{[1
]}

Qin, Shuai ^{[1
]}

Shu, Hanlin ^{[1
]}

Peng, Heyu ^{[1
]}

Yang, Xuran ^{[1
]}

Shen, Jingwen ^{[1
]}

Guo, Jiandi ^{[1
]}

Cao, Liangzhi ^{[1
]}

Wu, Hongchun ^{[1
]}

机构：

[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, 28 West Xianning Rd, Xian 710049, Peoples R China

来源：

EPJ NUCLEAR SCIENCES & TECHNOLOGIES | 2024年 / 10卷

基金：

中国国家自然科学基金;

关键词：

VARIANCE REDUCTION; REACTOR;

D O I：

10.1051/epjn/2024014

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

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.

引用

页数：10

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