Development of a steady state analysis code for molten salt reactor based on nodal expansion method
Yong Cui, J.G. Chen, Ming Dai, X. Z. Cai
Topics & Concepts
Molten salt reactorMolten saltNeutron transportNuclear engineeringThermal hydraulicsCoolantDelayed neutronNuclear reactor coreSpent nuclear fuelMaterials scienceMechanicsEnvironmental scienceNeutronFissionNuclear physicsThermodynamicsPhysicsHeat transferEngineeringNuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics