Concept design and neutronics analysis of a heat pipe cooled nuclear reactor with CERMET fuel
Xiaoyu Guo, Yuchuan Guo, Simao Guo, Guanbo Wang, Zeguang Li, Rundong Li, Zi Wang, Kan Wang
Topics & Concepts
CermetNuclear engineeringMaterials scienceNeutron transportBerylliumCriticalityCeramicComposite materialNeutronNuclear physicsEngineeringPhysicsNuclear reactor physics and engineeringNuclear Materials and PropertiesGraphite, nuclear technology, radiation studies