Research Topic

Safety Analysis of Nuclear Reactor Thermal-Hydraulics

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About this Research Topic

With the development and popularization of the nuclear power plant (NPP), reactor safety has attracted more and more public attention, and the inevitable radioactivity of reactor fuel brings both risks and challenges to the development of the nuclear industry. Therefore, research into nuclear safety ...

With the development and popularization of the nuclear power plant (NPP), reactor safety has attracted more and more public attention, and the inevitable radioactivity of reactor fuel brings both risks and challenges to the development of the nuclear industry. Therefore, research into nuclear safety technology, especially the prevention and mitigation of reactor accidents, is of great importance to the system optimization and safety evaluation of nuclear power plants.

This Research Topic focuses on all aspects of nuclear energy that are devoted to improving the current understanding of thermal hydraulics and safety analysis during nuclear industry application; including, but not limited to:

- thermal hydraulic experiments, primarily fundamental experimental research of two-phase flow, heat and mass transfer, nuclear critical heat flux and the evaluation of thermal physical properties.

- computational fluid dynamics technologies and applications, including new CFD models, methods and problem simulation and application in nuclear engineering.

- safety analysis and code development, primarily NPP system thermal hydraulic analysis, (including normal operation and beyond design-basis accident, system and phenomenon code development) and sub-channel analysis

- severe accident analysis and experiments, especially fuels and cladding material candling, fuel-coolant interaction, corium pool behavior, melt corium and concrete interaction, direct containment heating, hydrogen reaction, etc.

- instrumentation and measurement techniques, particularly innovations of methods or techniques in thermal and hydraulic parameter measurement.

- next generation reactor technology and advanced thermo-fluid system design, looking at Generation IV NPP concept design, molten salt reactors, supercritical water cooled reactors, gas-cooled fast reactors, sodium-cooled fast reactors, lead-cooled fast reactors, accelerator driven subcritical reactors, etc.

- other topics not mentioned but related to these areas.


Keywords: thermal hydraulics, experiments, CFD, two-phase flow, severe accidents


Important Note: All contributions to this Research Topic must be within the scope of the section and journal to which they are submitted, as defined in their mission statements. Frontiers reserves the right to guide an out-of-scope manuscript to a more suitable section or journal at any stage of peer review.

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