About this Research Topic
Nuclear fuels mainly include fuels and cladding materials, fuels and cladding structure, mechanical engineering, stress-strain, plastic deformation of fuels and cladding, oxidation of cladding, accident tolerance fuels materials development and thermal physical properties evaluation. Nuclear Thermal hydraulics mainly means NPP system thermal hydraulic analysis, including normal operation, beyond design basis accident and so on. NPP severe accident mainly include fuels and cladding materials candling, fuel-coolant interaction(FCI), debris bed heat transfer, core flow channel blockage, formation of melting pool, melt core and concrete interaction (MCCI). Core sub-channel means 2D analysis of NPP cores, to reveal the temperature and flow distribution in the core. Generation IV NPP concept design include very-high temperature reactor (VHTR), molten salt reactor (MSR), supercritical water cooled reactor (SCWR), gas cooled fast reactor (GFR), sodium cooled fast reactor (SFR), lead cooled fast reactor (LFR). Accelerator driven subcritical reactor can also be included. Experiment two-phase flow include the studying on heat transfer coefficient, nuclear critical heat flux in different nuclear industry structure. Computation fluid dynamics simulation means using CFD method to study nuclear projects. Applications of new methods is an inter-discipline, providing more opportunities to solve engineering problems in nuclear industry.
In this Research Topic, nuclear fuels, nuclear thermal hydraulics, nuclear power plant (NPP) severe accident, core sub-channel, generation IV NPP concept design, experiment two-phase flow, computation fluid dynamics simulation, and applications of new methods are all welcomed. Other topics not included but around these regions are also welcomed.
Keywords: Thermal Hydraulics, Two-Phase Flow, Severe Accident, Sub-Channel, Computation and Fluid Dynamics Simulations
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