Litcius/Paper detail

A review of CFD studies on thermal hydraulic analysis of coolant flow through fuel rod bundles in nuclear reactor

Mingjun Wang, Haoran Ju, Wu Jian, Hanrui Qiu, Kai Liu, Wenxi Tian, G.H. Su

2024Progress in Nuclear Energy64 citationsDOI

Topics & Concepts

Thermal hydraulicsComputational fluid dynamicsCoolantNuclear engineeringNuclear reactorFlow (mathematics)MechanicsMaterials scienceEnvironmental scienceNuclear physicsPhysicsHeat transferEngineeringNuclear Engineering Thermal-HydraulicsHeat transfer and supercritical fluidsNuclear reactor physics and engineering