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Fuel coolant interaction experiments in TROI using a UO2/ZrO2 mixture

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TLDR
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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This article is published in Nuclear Engineering and Design.The article was published on 2003-05-01. It has received 61 citations till now. The article focuses on the topics: Steam explosion & Corium.

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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.
Journal ArticleDOI

Melt jet-breakup and fragmentation phenomena in nuclear reactors: A review of experimental works and solidification effects

TL;DR: In this paper, a review summarizes experimental works on the fuel-coolant interaction (FCI) phenomenon, especially, fragmentation of a melt jet during a severe accident in an NPP, and special attention is paid to solidification effects.
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Journal ArticleDOI

Insight into steam explosions with corium melts in KROTOS

TL;DR: In this article, the authors describe two KROTOS tests in which ∼4 kg of corium melt was injected into a ∼1-m deep subcooled water pool and showed that the corium jet penetrated deep into the water while maintaining its shape.
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Corium melt quenching tests at low pressure and subcooled water in FARO

TL;DR: The first two corium melt quenching tests in subcooled water performed in the FAT FCI vessel of the FARO facility are described in this article, which involved 39 and 92 kg of 80 wt% UO 2 + 20 wt % ZrO 2 melt, respectively.
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Lessons learnt from FARO/TERMOS corium melt quenching experiments

TL;DR: In this paper, the influence of melt quantity and composition, water depth and initial pressure on quenching was assessed on the basis of seven tests performed under various conditions in the TERMOS vessel of the FARO facility at JRC-Ispra.
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Phenomenological studies on melt-coolant interactions in the ALPHA program

TL;DR: In this article, a series of experiments to investigate melt-coolant interactions have been performed as part of the ALPHA program at JAERI, where melt simulating a molten core was dropped into a pool of water and volume fractions of the melt, water and steam in the mixing region prior to the occurrence of spontaneous steam explosions were quantified.
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Experiments on the interactions of molten ZrO2 with water using TROI facility

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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