Articles citing this article

The Citing articles tool gives a list of articles citing the current article.
The citing articles come from EDP Sciences database, as well as other publishers participating in CrossRef Cited-by Linking Program. You can set up your personal account to receive an email alert each time this article is cited by a new article (see the menu on the right-hand side of the abstract page).

Cited article:

A multi-scale Mamba framework for advanced multi-layer photon shielding analysis

Junyi Chen, Chenghao Cao, Shaoning Shen, Tianyuan Guo and Jingang Liang
Radiation Physics and Chemistry 242 113626 (2026)
https://doi.org/10.1016/j.radphyschem.2026.113626

Coupled neutronics/thermal-hydraulics analysis of irregularly shaped reactor cores: application to helical cruciform fuel

Wenbin Han, Tao Zhang, Pengfei Shen, Jian Deng, Qi Lu and Shanfang Huang
Nuclear Engineering and Design 446 114592 (2026)
https://doi.org/10.1016/j.nucengdes.2025.114592

Fusion neutronics simulations with RMC: Key capabilities and techniques

Kok Yue Chan, Pengfei Shen, Zhaoyuan Liu, Songlin Liu, Zhe Chuan Tan, Yuanhao Gou, Shihang Jiang and Kan Wang
Fusion Engineering and Design 222 115532 (2026)
https://doi.org/10.1016/j.fusengdes.2025.115532

A review of Monte Carlo-based multiphysics coupling in nuclear reactor analysis

Shanfang Huang, Guodong Liu, Ying He, Xingyu Zhao, Zhigang Li, Yugao Ma, Meiming Qiu, Yongtang Wang, Haisheng Chen, Junren Hou, Kaiwen Li, Hao Luo, Chuan Lu and Kan Wang
Progress in Nuclear Energy 192 106178 (2026)
https://doi.org/10.1016/j.pnucene.2025.106178

A Simulated Comprehensive Photon Flux Shielding Spectra Dataset for Advanced Radiation Safety Assessment

Junyi Chen, Chenghao Cao, Shaoning Shen, Ben Qi, Ruihan Li and Jingang Liang
Scientific Data 12 (1) (2025)
https://doi.org/10.1038/s41597-025-05814-y

Simulation of UNCL experimental device for the reactor fuels based on reactor Monte Carlo code RMC

Yuanhao Gou, Conglong Jia, Dacai Zhang, Zhechuan Tan and Kan Wang
Nuclear Engineering and Design 443 114316 (2025)
https://doi.org/10.1016/j.nucengdes.2025.114316

Development and verification of transport and tally capabilities based on unstructured mesh in Reactor Monte Carlo code RMC

Jie Li, Pengfei Shen, Zhaoyuan Liu, Qing Li and Kan Wang
Nuclear Engineering and Technology 57 (6) 103404 (2025)
https://doi.org/10.1016/j.net.2024.103404