INVESTIGATION OF subscriptCOOLEDWATER DISCHARGE THROUGH SIMULATED STEAM GENERATOR TUBE CRACKS

The work presented here describes an investigation into the choked flow of initially subscriptcooled water through simulated steam generator tube cracks at pressures up to 7 MPa. The study of such flow is relevant to the prediction of leak flow rates from a nuclear reactor primary side to secondary side through cracks in steam generator tubes. A facility was designed to measure the leak rates and experiments were conducted on choking flow for …