Special Issues

Neutronic and Thermal-Hydraulic Analysis of Advanced Nuclear Reactors

Submission Deadline: 01 April 2026 View: 575 Submit to Special Issue

Guest Editors

Prof. Shichang Liu

Email: liu-sc@ncepu.edu.cn

Affiliation: School of Nuclear Science and Engineering, North China Electric Power University, Beinong Road No.2, Changping, Beijing, 102206, China

Homepage:

Research Interests: neutronics, particle transport

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Prof. Fudong Liu

Email: Liufudong1968@sina.com

Affiliation: Nuclear and radiation safety center, Ministry of Ecology and Environment, 9 Zhixing East Rd., FangShan, Beijing, 102400, China

Homepage:

Research Interests: radiation protection and environment protect

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Mr. Jinggang Li

Email: Jacky.li2016@qq.com

Affiliation: China Nuclear Power Technology Research Institute Co.,Ltd., ShenZhen, 518000, China

Homepage:

Research Interests: nuclear reactor design, nuclear engineering software

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Dr. Peng Zhang

Email: zhangpengg@cnpe.cc

Affiliation: Beijing Institute of Nuclear Engineering, China Nuclear Power Engineering Co. Ltd. No. 117, West 3Rd N. Road, Haidian, Beijing, 100840, China

Homepage:

Research Interests: computational reactor physics, innovative nuclear system design, multiphysics simulation, high performance computing

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Summary

The accelerated deployment of advanced nuclear reactors—such as small modular reactors (SMRs), Generation IV fast-spectrum, molten-salt, and high-temperature gas-cooled concepts—is pivotal to achieving deep-decarbonization targets and ensuring resilient, low-carbon baseload power. These designs promise enhanced safety, flexible grid integration, and resource utilization, yet their neutronic and thermal-hydraulic behaviors depart significantly from legacy light-water fleets. Multiphysics phenomena, including strong coupling between neutron kinetics, coolant flow, and heat transfer, introduce new challenges in reactor licensing, operation, and safety assessment.

This Special Issue provides a dedicated forum for cutting-edge research on coupled neutronics and thermal-hydraulic analysis of advanced reactors. We solicit original research papers and comprehensive reviews that advance multiscale modeling, high-fidelity simulation, experimental validation, and code development. Contributions should address fundamental physics, engineering methodologies, regulatory frameworks, and practical deployment experiences.

Suggested topics include:
· Advanced Reactor Design and Analysis;
· Reactor Physics, Thermal-hydraulics, and Safety;
· Nuclear Fuel and Materials;
· Uncertainty Quantification;
· CFD Analysis of Advanced Reactor;
· Advanced thorium uranium/uranium plutonium fuel cycle scheme;
· Transient accident safety of advanced nuclear energy systems;
· Research on Multi-physics Coupling of Advanced Nuclear Energy Systems;
· Radiation protection and environment protect;
· Other related topics in the field of advanced nuclear energy.

By consolidating the latest theoretical, computational, and experimental advances, this Special Issue aims to accelerate the safe, efficient, and economic deployment of next-generation nuclear technologies.


Keywords

neutronics, thermal-hydraulics, advanced reactors, multiphysics coupling, safety analysis, CFD, uncertainty quantification

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