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Works (12)

A simulation approach for start-up without secondary neutron sources of Hualong One: A Monte-Carlo-deterministic framework

Nuclear Engineering and Technology
2025-08 | Journal article
DOI: 10.1016/j.net.2025.103546
Contributors: Jiandi Guo; Zhouyu Liu; Qingming He; Danbin Huang; Liangzhi Cao; Hongchun Wu
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Crossref

Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCX

Nuclear Engineering and Technology
2024-12 | Journal article
DOI: 10.1016/j.net.2024.07.038
Contributors: Hongchun Wu; Shuai Qin; Yunzhao Li; Jinkang Shi; Qingming He; Liangzhi Cao
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Crossref

Study on Unstructured Mesh–Based Monte Carlo/Deterministic Coupled Particle Transport Calculation Method

Nuclear Science and Engineering
2024-11 | Journal article
DOI: 10.1080/00295639.2023.2295065
Contributors: Hanlin Shu; Liangzhi Cao; Qingming He; Qi Zheng; Tao Dai
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Crossref

The methods of CADIS-NEE and CADIS-DXTRAN in NECP-MCX and their applications

Nuclear Engineering and Technology
2024-07 | Journal article
DOI: 10.1016/j.net.2024.02.036
Contributors: Qingming He; Zhanpeng Huang; Liangzhi Cao; Hongchun Wu
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Crossref

Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX

Nuclear Engineering and Technology
2023-09 | Journal article
DOI: 10.1016/j.net.2023.05.029
Contributors: Shuai Qin; Yunzhao Li; Qingming He; Liangzhi Cao; Yongping Wang; Yuxuan Wu; Hongchun Wu
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Crossref

Calculation of thermal neutron scattering data of MgF2 and its effect on beam shaping assembly for BNCT

Nuclear Engineering and Technology
2023-04 | Journal article
DOI: 10.1016/j.net.2022.12.027
Contributors: Jiaqi Hu; Zhaopeng Qiao; Lunhe Fan; Yongqiang Tang; Liangzhi Cao; Tiejun Zu; Qingming He; Zhifeng Li; Sheng Wang
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Crossref

Particle-transport/depletion/activation/source-term coupling analysis for CFETR with NECP-MCX

Fusion Engineering and Design
2023-03 | Journal article
DOI: 10.1016/j.fusengdes.2022.113399
Contributors: Qingming He; Jie Li; Hanlin Shu; Liangzhi Cao; Hongchun Wu; Wei Shen
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Crossref

Extension of the subgroup method for self-shielding calculation of fully ceramic micro-encapsulated fuel

Annals of Nuclear Energy
2020-06 | Journal article
DOI: 10.1016/j.anucene.2019.107136
Contributors: Qingming He; Wen Yin; Zhouyu Liu; Tiejun Zu; Liangzhi Cao; Hongchun Wu
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Crossref

Development and validation of the depletion capability of the high-fidelity neutronics code NECP-X

Annals of Nuclear Energy
2020-04 | Journal article
DOI: 10.1016/j.anucene.2019.107096
Contributors: Xingjian Wen; Zhouyu Liu; Jun Chen; Kai Huang; Qingming He; Liangzhi Cao
Source: check_circle
Crossref

The on-the-fly subgroup method capable of treating spatial self-shielding, resonance interference and temperature distribution effects

Progress in Nuclear Energy
2020-01 | Journal article
DOI: 10.1016/j.pnucene.2019.103173
Contributors: Qingming He; Jun Chen; Zhouyu Liu; Liangzhi Cao; Hongchun Wu
Source: check_circle
Crossref

Error analysis of approximations and treatments commonly made in multi-group library and self-shielding calculation based on NECP-X

Annals of Nuclear Energy
2019-08 | Journal article
DOI: 10.1016/j.anucene.2019.03.012
Contributors: Qingming He; Zhouyu Liu; Liangzhi Cao; Hongchun Wu
Source: check_circle
Crossref

Improved resonance calculation of fluoride salt-cooled high-temperature reactor based on subgroup method

Annals of Nuclear Energy
2016-02 | Journal article
DOI: 10.1016/j.anucene.2015.11.005
Contributors: Qingming He; Liangzhi Cao; Hongchun Wu; Tiejun Zu
Source: check_circle
Crossref

Peer review (5 reviews for 3 publications/grants)

Review activity for Annals of nuclear energy. (1)
Review activity for Nuclear engineering and design. (1)
Review activity for Nuclear engineering and technology. (3)
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