Improvement of GAMMA+ code for system transient and thermo-fluid safety analysis of sodium-cooled fast reactors
Nam-il Tak, Hong S. Lim, Jonggan Hong, Jung Yoon, Byung Ha Park, Jaehyuk Eoh
Topics & Concepts
Sodium-cooled fast reactorNuclear engineeringTransient (computer programming)Pressure dropReliability (semiconductor)Heat exchangerHeat transferComputer scienceMechanical engineeringSimulationReliability engineeringEngineeringMechanicsPhysicsThermodynamicsProgramming languagePower (physics)Nuclear reactor physics and engineeringNuclear Engineering Thermal-HydraulicsNuclear Materials and Properties