Design of the CAREM nuclear reactor core with dual cooled annular fuel and optimizing the thermal-hydraulic, natural circulation, and neutronics parameters
Sh. Nasiri, G.R. Ansarifar, Mohammad Hossein Esteki
Topics & Concepts
Neutron transportNatural circulationNuclear engineeringCoolantThermal hydraulicsNuclear reactor coreMaterials scienceDecay heatRADIUSSpent nuclear fuelResearch reactorShutdownNuclear reactorEnvironmental scienceMechanicsNeutronHeat transferNuclear physicsPhysicsComputer scienceEngineeringComputer securityNuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics