H
Hee-Dong Kim
Publications - 31
Citations - 423
Hee-Dong Kim is an academic researcher. The author has contributed to research in topics: Reactor pressure vessel & Corium. The author has an hindex of 11, co-authored 31 publications receiving 366 citations.
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Fuel coolant interaction experiments in TROI using a UO2/ZrO2 mixture
TL;DR: In this paper, the results of steam explosion experiments using reactor material carried out under the Test for Real cOrium Interaction with water (TROI) program are discussed.
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Spray effect on the behavior of hydrogen during severe accidents by a loss-of-coolant in the APR1400 containment
TL;DR: In this article, the effects of spray activation on the behavior of steam and hydrogen which are produced in the reactor vessel and released into the containment of the APR1400 nuclear power plant during hypothetical severe loss-of-coolant accidents (LOCA), the 3-dimensional CFD code GASFLOW was used.
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Experiments on the interactions of molten ZrO2 with water using TROI facility
JinHo Song,I.K. Park,Y.J. Chang,Y.S. Shin,Ji Hyun Kim,Beong Tae Min,Seong-Wan Hong,Hee-Dong Kim +7 more
TL;DR: In this paper, a series of tests using several kg of ZrO 2 where the melt/water interaction is made in a heated water pool at 30-95°C, either a quenching or a spontaneous steam explosion was observed.
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The effect of corium composition and interaction vessel geometry on the prototypic steam explosion
TL;DR: In this article, the results of steam explosion experiments using molten material consisting of UO 2 and ZrO 2 mixture, which is called corium, to simulate a prototypic steam explosion in a nuclear reactor during a postulated severe accident were discussed.
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Three-dimensional behaviors of the hydrogen and steam in the APR1400 containment during a hypothetical loss of feed water accident
TL;DR: In this paper, an analysis of the hydrogen and steam behavior during a total loss of feed water (LOFW) accident in the APR1400 containment has been conducted by using the computational fluid dynamics (CFD) code GASFLOW.