HEART, a specific code for thermal-electrical analysis of heat pipe cooled nuclear reactor
Zeqin Zhang, Chenglong Wang, Kailun Guo, Jinlu Huang, Suizheng Qiu, G.H. Su, Wenxi Tian
Topics & Concepts
Nuclear engineeringMaterials scienceNuclear reactorThermalThermodynamicsMechanicsPhysicsEngineeringNuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics