Litcius/Paper detail

Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT

Richard Hernandez, Charles P Folsom, Nicolas Woolstenhulme, Colby Jensen, John D. Bess, Jacob P. Gorton, Nicholas R. Brown

2020Progress in Nuclear Energy33 citationsDOIOpen Access PDF

Topics & Concepts

Critical heat fluxCoolantNuclear engineeringSubcoolingMaterials scienceBoilingThermal hydraulicsCladding (metalworking)Heat transferNucleate boilingPressurizerNuclear reactorTransient (computer programming)Heat fluxThermodynamicsComposite materialComputer scienceOperating systemPhysicsEngineeringHeat Transfer and Boiling StudiesNuclear Engineering Thermal-HydraulicsNuclear Materials and Properties
Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT | Litcius