Neutronics and thermal-hydraulics coupling analysis using the FLUENT code and the RELAP5-3D code for a molten salt fast reactor
Hiroyasu Mochizuki
Topics & Concepts
FluentNeutron transportThermal hydraulicsDelayed neutronNuclear engineeringComputational fluid dynamicsPipingMolten saltDecay heatInflowControl rodMechanicsMaterials scienceNeutronThermodynamicsHeat transferNeutron temperatureNuclear physicsEngineeringPhysicsNuclear reactor physics and engineeringNuclear Engineering Thermal-HydraulicsNuclear Materials and Properties