Intentional Depressurization of Steam Generator Secondary Side during a PWR Small-Break Loss-Coolant Accident
The consequence of intentional depressurization of the steam generator (SG) secondary side during a small break loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR) was studied using the ROSA-IV Large Scale Test Facility (LSTF). The LSTF is a 1:48 volumetrically scaled full-height model of a Westinghouse-type PWR. The experiment simu- lated a 0.5% cold leg small-break LOCA with total failure of high pressure injection (HPI) system. The SG secondary-side atmospheric relief valve (ARV) was latched open after the core top region was uncovered. Then, the primary pressure closely followed the secondary pressure and dropped to the accumulator (ACC) injection pressure of 4.51MPa before the core became severely overheated. A post test analysis, which was performed using the RELAP5/ MOD2 code with modifications made by the authors, predicted well the primary and secondary side responses during this experiment.
- Journal of nuclear science and technology
Journal of nuclear science and technology 32(2), 101-110, 1995-02-25
Atomic Energy Society of Japan