A neutronic evaluation of a thorium-based molten salt breeder reactor
Clarysson A. M. da Silva, Isabella R. Magalhães, María Lorduy-Alós, S. Gallardo, Cláubia Pereira, Antonella Lombardi Costa, G. Verdú
Topics & Concepts
Nuclear engineeringMOX fuelThorium fuel cycleFissile materialBurnupPlutoniumSpent nuclear fuelBreeder reactorMolten salt reactorEnriched uraniumMolten saltMaterials scienceActinideEnvironmental scienceWaste managementUraniumRadiochemistryNeutronNuclear physicsNuclear chemistryChemistryEngineeringPhysicsMetallurgyNuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Physics and Applications