The development of nuclear reactor three-dimensional neutronic thermal–hydraulic coupling code: CorTAF-2.0
Zhengyang Dong, Kai Liu, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su
Topics & Concepts
Thermal hydraulicsNuclear engineeringNeutron transportCoupling (piping)Nuclear reactor coreCore (optical fiber)Benchmark (surveying)Nuclear reactorMechanical engineeringNeutronEngineeringMechanicsNuclear physicsPhysicsHeat transferTelecommunicationsGeodesyGeographyNuclear reactor physics and engineeringNuclear Engineering Thermal-HydraulicsNuclear Materials and Properties