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자료유형
학술저널
저자정보
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제48권 제6호
발행연도
2016.1
수록면
1,330 - 1,337 (8page)

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초록· 키워드

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A visualization test of the fuelecoolant interaction in the Test for Real cOrium Interactionwith water (TROI) test facility was carried out. To experimentally simulate the In-Vesselcorium Retention (IVR)- External Reactor Vessel Cooling (ERVC) conditions, prototypiccorium was released directly into the coolant water without a free fall in a gas phase beforemaking contact with the coolant. Corium (34.39 kg) consisting of uranium oxide and zirconiumoxide with a weight ratio of 8:2 was superheated, and 22.54 kg of the 34.39 kgcorium was passed through water contained in a transparent interaction vessel. An imageof the corium jet behavior in the coolant was taken by a high-speed camera every millisecond. Thermocouple junctions installed in the vertical direction of the coolant were cutsequentially by the falling corium jet. It was clearly observed that the visualization imageof the corium jet taken during the fuelecoolant interaction corresponded with the temperaturevariations in the direction of the falling melt. The corium penetrated through thecoolant, and the jet leading edge velocity was 2.0 m/s. Debris smaller than 1mmwas 15% ofthe total weight of the debris collected after a fuelecoolant interaction test, and the massmedian diameter was 2.9 mm.

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