Summary of ROSA-IV LSTF first-phase test program — Integral simulation of PWR small-break LOCAs and transients -

Significant experimental results obtained at the ROSA-IV Large-Scale Test Facility (LSTF) during the first phase of the test program (1985–1988) are summarized. The LSTF is a volumetrically scaled, full-height, full-pressure simulator of a Westinghouse-type four-loop (3423 MW thermal power) pressurized water reactor (PWR). The LSTF first-phase program investigated the fundamental PWR thermal-hydraulic responses during small-break loss-of-coolant accidents (SBLOCAs) and transients. The test matrix included twenty-nine SBLOCA tests, three abnormal transient tests and ten steady-state natural circulation tests.