Sc23667-htwr.part4.rar < Working ◎ >

The necessity of advanced safety analyses for high-temperature water reactors (HTWR).

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

To validate the heat transfer characteristics and pressure drop behavior in a core assembly. sc23667-HTWR.part4.rar

Application of Navier-Stokes equations with turbulence modeling in modern thermal-hydraulic codes. sc23667-HTWR.part4.rar