High-fidelity neutronics and thermal-hydraulics analysis of helical cruciform fuel based on small modular FHR
Xingguang Zhou, Dalin Zhang, Xinyu Li, Wenxi Tian, G.H. Su, Suizheng Qiu
Topics & Concepts
Neutron transportThermal hydraulicsNuclear engineeringModular designNuclear reactor coreMaterials scienceCoolantHeat transferHydraulicsMechanicsMechanical engineeringComputer scienceNuclear physicsPhysicsEngineeringThermodynamicsNeutronOperating systemNuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear and radioactivity studies