Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor
Saeed A. Alameri, Mohammad Alrwashdeh
Topics & Concepts
BurnupNuclear engineeringMaterials scienceNeutron transportNuclear reactor coreBlanketControl rodCoolantCoatingDelayed neutronNeutronNeutron temperatureNuclear physicsComposite materialPhysicsEngineeringNuclear reactor physics and engineeringNuclear Materials and PropertiesGraphite, nuclear technology, radiation studies