Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
5477901 | Nuclear Engineering and Technology | 2016 | 8 Pages |
Abstract
A visualization test of the fuel-coolant interaction in the Test for Real cOrium Interaction with water (TROI) test facility was carried out. To experimentally simulate the In-Vessel corium Retention (IVR)- External Reactor Vessel Cooling (ERVC) conditions, prototypic corium was released directly into the coolant water without a free fall in a gas phase before making contact with the coolant. Corium (34.39Â kg) consisting of uranium oxide and zirconium oxide with a weight ratio of 8:2 was superheated, and 22.54Â kg of the 34.39Â kg corium was passed through water contained in a transparent interaction vessel. An image of 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 cut sequentially by the falling corium jet. It was clearly observed that the visualization image of the corium jet taken during the fuel-coolant interaction corresponded with the temperature variations in the direction of the falling melt. The corium penetrated through the coolant, and the jet leading edge velocity was 2.0Â m/s. Debris smaller than 1Â mm was 15% of the total weight of the debris collected after a fuel-coolant interaction test, and the mass median diameter was 2.9Â mm.
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Authors
Young Su Na, Seong-Ho Hong, Jin Ho Song, Seong-Wan Hong,