Comparison of cobra-tf and vipre-01 against low flow code assessment problems

Engineering

• Subchannel 100%
• Relative Strength 100%
• Oak Ridge 50%
• Primary Flow 50%
• Small Modular Reactor 50%
• Natural Circulation 50%
• Analysis Code 50%
• Rod Bundle 50%
• Reactor Core 50%
• Power Flow 50%
• Coolant Flow 50%
• Identify Area 50%
• Subchannel Analysis 50%
• Exit Quality 50%
• Representative Set 50%
• Safety Analysis 50%
• Two-Phase Flow 50%
• Pressure Drop 50%
• Channel Flow 50%
• Model Test 50%
• Porosity 50%
• United States 50%
• Nuclear Engineering 50%