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http://dx.doi.org/10.1016/j.net.2016.06.010

Fuel-Coolant Interaction Visualization Test for In-Vessel Corium Retention External Reactor Vessel Cooling (IVR-ERVC) Condition  

Na, Young Su (Severe Accident and PHWR Safety Research Division, Korea Atomic Energy Research Institute)
Hong, Seong-Ho (Severe Accident and PHWR Safety Research Division, Korea Atomic Energy Research Institute)
Song, Jin Ho (Severe Accident and PHWR Safety Research Division, Korea Atomic Energy Research Institute)
Hong, Seong-Wan (Severe Accident and PHWR Safety Research Division, Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.48, no.6, 2016 , pp. 1330-1337 More about this Journal
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 (34.39 kg) consisting of uranium oxide and zirconium oxide with a weight ratio of 8:2 was superheated, and 22.54 kg of the 34.39 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 2.0 m/s. Debris smaller than 1 mm was 15% of the total weight of the debris collected after a fuel-coolant interaction test, and the mass median diameter was 2.9 mm.
Keywords
Fuel-Coolant Interaction; Severe Accident; Steam Explosion; Test for Real cOrium Interaction with water (TROI);
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
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