Part 4 focuses on transient response to Loss of Forced Cooling (LOFC) scenarios. 2. Methodology and Modeling (SC23667)
Find official documentation on the if that is what the paper refers to.
To validate the heat transfer characteristics and pressure drop behavior in a core assembly.
The study demonstrates that the SC23667 design meets safety standards for core thermal limits during transients. The developed numerical codes show high accuracy in predicting thermal-hydraulic phenomena within the reactor core.
Part 4 focuses on transient response to Loss of Forced Cooling (LOFC) scenarios. 2. Methodology and Modeling (SC23667)
Find official documentation on the if that is what the paper refers to. sc23667-HTWR.part4.rar
To validate the heat transfer characteristics and pressure drop behavior in a core assembly. Part 4 focuses on transient response to Loss
The study demonstrates that the SC23667 design meets safety standards for core thermal limits during transients. The developed numerical codes show high accuracy in predicting thermal-hydraulic phenomena within the reactor core. sc23667-HTWR.part4.rar
