Neutronic performance of fully ceramic microencapsulated of uranium oxycarbide and uranium nitride composite fuel in SMR
Yahya A. Alzahrani, Khurram Mehboob, Daud Mohamad, Abdulsalam M. Alhawsawi, Fouad A. Abolaban
Topics & Concepts
Nuclear engineeringFissile materialMaterials scienceMOX fuelNuclear fuelCriticalityEnvironmental scienceUranium dioxideBurnupUraniumEngineeringMetallurgyNuclear physicsNeutronPhysicsNuclear Materials and PropertiesNuclear reactor physics and engineeringFusion materials and technologies