Stratification in Nuclear Reactor Components Conference Paper uri icon

abstract

  • Abstract Several experiments have recorded loop stratification at a recent test performed at the Rig of Safety Assessment (ROSA) project at the Japanese Atomic Energy Research Institutes Large Scale Test. This facilty (LSTF) is used for for the advanced nuclear reactor AP600 simulation. Prediction of stratification in reactor coolant loops is of interest during accident conditions. The present study attempts to develop the criteria for stratification in the coolant loops based on data from the LSTF experiments. The first criteria was developed for addressing injection-induced stratification. The second criteria applies to downcomer/cold leg junction stratification. Both criteria provided predictions consistent with LSTF data.

name of conference

  • Thermal Science of Advanced Steam Generators/Heat Exchangers

published proceedings

  • Thermal Science of Advanced Steam Generators/Heat Exchangers

author list (cited authors)

  • Randorf, J. A., & Hassan, Y. A.

citation count

  • 0

complete list of authors

  • Randorf, JA||Hassan, YA

publication date

  • November 1996