Neutronic characteristics and feasibility analysis of micro-heterogeneous duplex ThO2-UO2 fuel pin in PWR
Jiecong Li, Xuezhong Li, Jiejin Cai
Topics & Concepts
BurnupNuclear engineeringSpent nuclear fuelThorium fuel cyclePlutonium-240Nuclear fuelPlutoniumMOX fuelUranium dioxideMaterials scienceEnriched uraniumPlutonium-239Environmental scienceUraniumWaste managementFissionRadiochemistryNuclear physicsNeutronChemistryEngineeringPhysicsMetallurgyNuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics