1987 年 29 巻 1 号 p. 18-30
The Large Scale Test Facility (LSTF) of the Rig of Safety Assessment (ROSA)-IV Program is an integral test facility to investigate thermal-hydraulic response of a pressurized water reactor (PWR) system during small break loss-of-coolant accidents (LOCAs) and operational transients. The LSTF is volumetrically scaled at 1/48 and has the same height as the PWR. The construction of the LSTF was completed in May 1985 and several small break LOCAs, TMI-2 accident type simulation and natural circulation tests have been successfully conducted. Presented in the present report are outline of the test program at the LSTF and some test results including transient core liquid level depression during cold leg small-break LOCAs, break orientation effect in cold leg small-break LOCAs on the system transient and thermal-hydraulic phenomena during the TMI-2 type multifailure accident simulation test.