Comparison of the TRAC (Transient Reactor Analysis Code) Calculational Results for the Slab Core Test Facility Model and the Reference German Pressurized Water Reactor during Reflood

摘要

A calculation through reflood and full-rod quenching has been made with the TRAC-PD2 model for the Slab Core Test Facility. The model was intended to simulate a typical German pressurized water reactor (GPWR) with combined hot-leg and cold-leg emergency core coolant injection. The results of this calculation were compared with a similar calculation for the GPWR. There was good overall agreement, with similar phenomena observed in both calculations for such parameters as liquid inventories, mass flow rates, upper plenum subcooling, and temperatures and pressures.