Test results of Run-3 in steam generator safety test facility (SWAT-3); (Report No.4; Large leak sodium-water reaction test)

Hiroi, Hiroshi*; not registered; not registered; not registered; not registered; not registered

Large Leak sodium-water reaction tests have been carried out using SWAT-1 rig and SWAT-3 facility in PNC O-arai Engineering Center to obtain the data on the safe design of the prototype LMFBR Monju's steam generator against large leak accident. This report gives the results of SWAT-3 run-3 test. In run-3 test, the heat transfer tube bundle of the evaporator, fabricated by TOSHIBA/IHI, were used, and the pressure relief line was located at the side of evaporator. The water injection rate to the evaporator was 8.8 kg/sec, which corresponds to test scale of 3.5 tubes failure in actual size system according to iso-velocity modeling. Measurements were made of pressure, strain, temperature, sodium level, void, thrust load, acceleration, displacement, flow rate, and so on. Initial spike pressure was 16 kg/cma nearest to injection point, and the maximun quasi-steady pressure in evaporator was 5.0 kg/cma. The rupture disc of evaporator was bursted at 0.56 sec after water injected, and the pressure relief system was well functioned. No secondary tube failure was observed.