About this Research Topic
This Research Topic is Volume II of a series. The previous volume, which has attracted over 20,000 views can be found here: Experimental and Simulation Research on Nuclear Reactor Thermal-Hydraulics
The research on nuclear reactor thermal-hydraulics have achieved outstanding progresses in the past decades. In recent years, basic research on multiphase flow dynamics and corresponding measurement technology, as well as preliminary research on Gen IV reactors based on experiments and simulations are attracting more and more attention. However, the inside complicated physics and outside extreme conditions will also bring risks and challenges to the development of nuclear industry.
Therefore, this Research Topic aims to promote the novel experimental and numerical investigations on relevant issues refer to nuclear reactor thermal-hydraulics, which is of great significance to the system optimization and safety evaluation of nuclear power plants. The topic includes but not limited to:
• Advances in instrumentation for high resolution measurement of multiphase flow;
• Simulation and verification with CFD and codes on multiphase flow;
• Thermal hydraulic problems with coupled thermo-chemical-mechanical phenomena;
• Thermal hydraulic problems in sodium cooled and lead cooled fast reactors;
• Thermal hydraulic problems in high temperature gas cooled reactor;
• Thermal hydraulic problems in small modular reactors;
• Thermal hydraulic problems in space nuclear power and heat pipe microreactor;
• Severe accidents and mitigation measures of nuclear power plant;
• Other related reactor thermal hydraulic problems.
The research on nuclear reactor thermal-hydraulics have achieved outstanding progresses in the past decades. In recent years, basic research on multiphase flow dynamics and corresponding measurement technology, as well as preliminary research on Gen IV reactors based on experiments and simulations are attracting more and more attention. However, the inside complicated physics and outside extreme conditions will also bring risks and challenges to the development of nuclear industry.
Therefore, this Research Topic aims to promote the novel experimental and numerical investigations on relevant issues refer to nuclear reactor thermal-hydraulics, which is of great significance to the system optimization and safety evaluation of nuclear power plants. The topic includes but not limited to:
• Advances in instrumentation for high resolution measurement of multiphase flow;
• Simulation and verification with CFD and codes on multiphase flow;
• Thermal hydraulic problems with coupled thermo-chemical-mechanical phenomena;
• Thermal hydraulic problems in sodium cooled and lead cooled fast reactors;
• Thermal hydraulic problems in high temperature gas cooled reactor;
• Thermal hydraulic problems in small modular reactors;
• Thermal hydraulic problems in space nuclear power and heat pipe microreactor;
• Severe accidents and mitigation measures of nuclear power plant;
• Other related reactor thermal hydraulic problems.
Keywords: Thermal Hydraulics, Experiments, Simulation, Two-Phase Flow, Severe Accident
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