Burnup optimization of once-through molten salt reactors using enriched uranium and thorium
Menglu Tan, Guifeng Zhu, Zhengde Zhang, Yang Zou, Xiaohan Yu, Chenggang Yu, Ye Dai, Rui Yan
Topics & Concepts
BurnupMolten salt reactorMolten saltThorium fuel cycleUraniumNuclear engineeringEnriched uraniumLiquid fluoride thorium reactorThoriumVolume (thermodynamics)Nuclear reactor coreSpent nuclear fuelGraphitePlutoniumNuclear fuelMaterials scienceNatural uraniumNuclear fuel cycleMOX fuelRadiochemistryChemistryFuel cycleMetallurgyEngineeringPhysicsThermodynamicsNuclear reactor physics and engineeringGraphite, nuclear technology, radiation studiesNuclear Materials and Properties