Stratification in nuclear reactor components
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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 Institute's Large Scale Test. This facility (LSTF) is used for the advanced nuclear factor 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.
author list (cited authors)
Randorf, J. A., & Hassan, Y. A.