Recent Advances in DSNP-A Simulation Language for Dynamic Simulation of Nuclear Power-Plant

Abstract

The DSNP was recently upgraded to permit one dimensional representation of the flow through the fuel channel in the core using the drift-flux approximation, and the Chexal-Lellouche correlation to calculate the slip velocity. Several test cases were executed simulating the AP600 PWR. Comparison of the channel model with COBRA-41 calculations have shown good agreement. It was found that the previous homogeneous equilibrium model produced adequate results for power plant simulation until boiling conditions appear in a fuel channel.