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Core and blanket thermal–hydraulic analysis of a molten salt fast reactor based on coupling of OpenMC and OpenFOAM

Bin Deng, Yong Cui, Jingen Chen, Long He, Shaopeng Xia, Chenggang Yu, Fan Zhu, X. Z. Cai

2020Nuclear Science and Techniques22 citationsDOI

Topics & Concepts

BlanketMolten saltThermal hydraulicsCoolantNuclear engineeringNeutron transportMaterials scienceMechanicsEnvironmental scienceHeat transferThermodynamicsPhysicsNuclear physicsNeutronEngineeringComposite materialMetallurgyNuclear reactor physics and engineeringNuclear Materials and PropertiesFusion materials and technologies
Core and blanket thermal–hydraulic analysis of a molten salt fast reactor based on coupling of OpenMC and OpenFOAM | Litcius