抄録
ROSA-II Test Program is intended to clarify thermal and hydrodynamic behavior in a primary cooling system of pressurized water reactor during a postulated loss-of-coolant accident by an integral test facility, ROSA-II. Thirty eight test runs were performed from February, 1974 to September, 1975.
The present report gives the purpose of the test program, the qualitative investigation of fluid behavior, a description of the test facility and some experimental results of a cold-leg break test. The results are as follows.
(1) Stored heat of the broken and the unbroken loop steam generators has considerable effect on flow behavior in the primary system.
(2) Accumulator water injected into the cold-leg piping flows out through the break. However, the coolability of injected water from low pressure coolant injection system into the hot-leg piping is enhanced by the preceded injection of accumulator water.
