Assessing the benefit of thorium fuel in a once through molten salt reactor
R. Andika Putra Dwijayanto, Fitria Miftasani, Andang Widi Harto
Topics & Concepts
Thorium fuel cycleMolten saltThoriumMolten salt reactorNuclear engineeringLiquid fluoride thorium reactorFuel cycleUranium-233Environmental scienceNuclear reactor coreMaterials scienceMOX fuelPlutoniumNuclear physicsPhysicsUraniumMetallurgyEngineeringNuclear reactor physics and engineeringNuclear Materials and PropertiesGraphite, nuclear technology, radiation studies