Latest Advances and Prospects of Thermal-Hydraulics in Nuclear Power System
A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".
Deadline for manuscript submissions: closed (20 June 2024) | Viewed by 521
Special Issue Editors
Interests: flow and heat transfer of multiphase flow; flow and heat transfer in porous media; reactor thermal-hydraulics and nuclear power safety; big data and data-driven
Special Issues, Collections and Topics in MDPI journals
Interests: reactor thermal-hydraulics and nuclear power safety; boiling heat transfer; critical heat flux; flow and boiling induced vibration; intelligent measurement technique
Interests: reactor thermal-hydraulics; safety analysis and PRA for light water reactors; currently with a focus on severe accident research including experimental study and code development
Special Issue Information
Dear Colleagues,
Nuclear energy is one of the carbon-free energy sources that are highly efficient. It has been one of the primary sources of energy in the world and represents a promising source for the increasing future demand.
Thermal hydraulics studies in nuclear power systems are essential to the design and safety demands of nuclear reactors, which mainly focused on the issues of how fluids flow, behave, and interact with different structures to transfer heat between the structure and the fluid. Key phenomena include conduction, convection, radiation heat transfer, phase change, and single- and multi-phase flows in nuclear power systems. As technologies move from water-cooled light water reactors to a myriad of options for cooling in new reactor designs, studies in this area cover water, gas, molten salt, and liquid metal coolants for advanced fission and fusion systems, as well as transport and mixing processes that occur inside reactor containment structures and in environmental systems, and both computational and experimental thermal hydraulic characterizations are at the forefront of maintaining reactor safety.
The Special Issue aims to provide a platform for the latest high-quality progress in the area of Thermal-Hydraulics in Nuclear Power Systems. The scope of the Special Issue includes all aspects of theoretical derivation and analysis, model development and simulation, experimental investigation and engineering application. Submitted articles should contribute to a better understanding of the thermal-hydraulic phenomena and their physics laws. The Special Issue will also consider the publication of state-of-the-art reviews to highlight the possible future direction from the professional insights of world-renowned researchers. Scientific and technical contributions include, but are not limited to:
- Fundamental thermal-hydraulics;
- Experimental thermal-hydraulics;
- Computational thermal-hydraulics;
- Code development and applications;
- Thermal hydraulics and safety;
- Thermal hydraulics of advanced reactors;
- Thermal hydraulics of nuclear installations;
- Severe accidents, phenomena, modeling, and experiments.
Dr. Liangxing Li
Dr. Shengjie Gong
Guest Editors
Yidan Yuan
Guest Editor Assistant
Manuscript Submission Information
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Keywords
- nuclear power
- nuclear reactor
- thermal-hydraulics
- lead-cooled fast reactors
- sodium-cooled fast reactors
- high-temperature gas-cooled reactors
- supercritical water reactors
- molten salt reactors
- pressurized water reactors
- boiling water reactors
- two-phase flow
- heat transfer
- critical heat flux
- pressure drops
- flow resistance
- experiments
- numerical simulations
- accident analysis
- verification and validation
- numerical models development
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