Neutronic and thermal analysis of heat pipe cooled graphite moderated micro reactor
Faisal Aldebie, Kevin Fernández-Cosials, Yassin A. Hassan
Topics & Concepts
Nuclear engineeringShutdownControl rodBurnupDecay heatMaterials scienceNuclear reactor coreCriticalityHeat fluxResearch reactorCore (optical fiber)Nuclear reactorMechanical engineeringHeat transferMechanicsNuclear physicsEngineeringNeutronPhysicsComposite materialNuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Physics and Applications