Effect of critical flow model in MARS-KS code on uncertainty quantification of large break Loss of coolant accident (LBLOCA)

Keyphrases

• Uncertainty Quantification 100%
• Critical Flow Model 100%
• Reactor Safety 100%
• Thermal Non-equilibrium 100%
• Multidimensional Analysis 100%
• SBLOCA 100%
• Length-diameter Ratio 60%
• Uncertainty Range 60%
• Equilibrium Factor 60%
• Nuclear Power Plant 40%
• Discharge Time 40%
• Discharge Coefficient 40%
• Design Basis Accident 40%
• Critical Flow 40%
• Small Length 20%
• Three-parameter 20%
• System Code 20%
• Geometric Effect 20%
• Model Calibration 20%
• Flow Phenomena 20%
• Uncertainty Parameters 20%
• Power Reactor 20%
• Regulatory Assessment 20%
• Marviken 20%
• Break Flow 20%
• Peak Cladding Temperature 20%
• Data Assimilation Method 20%

Engineering

• Flow Model 100%
• Dimensional Analysis 100%
• Critical Flow 100%
• Loss of Coolant Accidents 100%
• Uncertainty Quantification 100%
• Reactor Safety 100%
• Nonequilibrium 80%
• Diameter Ratio 60%
• Nuclear Power Plant 40%
• Discharge Coefficient 40%
• Design Basis Accident 40%
• Test Data 20%
• Nonequilibrium State 20%
• Model Calibration 20%
• Parameter Uncertainty 20%
• Transition Point 20%
• Flow Phenomenon 20%
• Test Facility 20%
• Ruptured Pipe 20%
• Power Reactor 20%