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Statements

Subject Item
n2:RIV%2F61388980%3A_____%2F15%3A00439373%21RIV15-AV0-61388980
rdf:type
n9:Vysledek skos:Concept
dcterms:description
The article is focused on the hydrogen release by chemical reaction of Fuel and Coolant (FCR) during the molten Fuel-Coolant Interaction (FCI) and its impact on the steam explosion (SE) efficiency. Samples of debris coming from several FCI tests have been characterized by solid-state analytical techniques. Two kinds of tests have been analyzed: (i) Experiments using simulant materials (MISTEE, PREMIX, ECO FCI experiments) and tests using prototypic corium i.e.; in the U-Zr-O system (KROTOS experiments). The nonradioactive melts produce during FCI from negligible amounts of hydrogen up to 3.6 g per kg of melt. It was found that UO2-ZrO2melt solidifies during FCI into face-centered (Fm3m) crystal cell forming a U1-xZrxO2+ysolid solution. The oxygen over-stoichiometry of the solid solution is the evidence of FCR and release of hydrogen. A method combining chemical analysis by Energy Dispersive X-ray Spectrometry (SEM/EDS) and X-ray Powder Diffraction (XRD) allowed the determination of the oxygen over-stoichiometry y. Therefore, it has been indirectly estimated how much hydrogen was formed during the chemical reaction between hot corium and water. These data are provided for KROTOS KS2, KS4 and KS5 tests performed in the frame of the OECD/NEA Serena phase-2 project. It has been shown that up to i.e.; 4.7 g of H2per kg of delivered corium melt can be formed by the reaction stoichiometric or sub-oxidized UO2-ZrO2melts with water. The oxygen over-stoichiometry of the U1-xZrxO2+ydebris (initially x = 0.48 for KS2; x = 0.35 for KS4; x = 0.38 and y = -0.37 for KS5) varied between 0.107 y 0.167. The hydrogen formation during FCI is primarily linked to the melt composition and secondary to the size of the fragmented melt droplets. The article is focused on the hydrogen release by chemical reaction of Fuel and Coolant (FCR) during the molten Fuel-Coolant Interaction (FCI) and its impact on the steam explosion (SE) efficiency. Samples of debris coming from several FCI tests have been characterized by solid-state analytical techniques. Two kinds of tests have been analyzed: (i) Experiments using simulant materials (MISTEE, PREMIX, ECO FCI experiments) and tests using prototypic corium i.e.; in the U-Zr-O system (KROTOS experiments). The nonradioactive melts produce during FCI from negligible amounts of hydrogen up to 3.6 g per kg of melt. It was found that UO2-ZrO2melt solidifies during FCI into face-centered (Fm3m) crystal cell forming a U1-xZrxO2+ysolid solution. The oxygen over-stoichiometry of the solid solution is the evidence of FCR and release of hydrogen. A method combining chemical analysis by Energy Dispersive X-ray Spectrometry (SEM/EDS) and X-ray Powder Diffraction (XRD) allowed the determination of the oxygen over-stoichiometry y. Therefore, it has been indirectly estimated how much hydrogen was formed during the chemical reaction between hot corium and water. These data are provided for KROTOS KS2, KS4 and KS5 tests performed in the frame of the OECD/NEA Serena phase-2 project. It has been shown that up to i.e.; 4.7 g of H2per kg of delivered corium melt can be formed by the reaction stoichiometric or sub-oxidized UO2-ZrO2melts with water. The oxygen over-stoichiometry of the U1-xZrxO2+ydebris (initially x = 0.48 for KS2; x = 0.35 for KS4; x = 0.38 and y = -0.37 for KS5) varied between 0.107 y 0.167. The hydrogen formation during FCI is primarily linked to the melt composition and secondary to the size of the fragmented melt droplets.
dcterms:title
Prototypic corium oxidation and hydrogen release during the Fuel-Coolant Interaction Prototypic corium oxidation and hydrogen release during the Fuel-Coolant Interaction
skos:prefLabel
Prototypic corium oxidation and hydrogen release during the Fuel-Coolant Interaction Prototypic corium oxidation and hydrogen release during the Fuel-Coolant Interaction
skos:notation
RIV/61388980:_____/15:00439373!RIV15-AV0-61388980
n3:aktivita
n14:I
n3:aktivity
I
n3:cisloPeriodika
JAN
n3:dodaniDat
n10:2015
n3:domaciTvurceVysledku
n6:4581792 n6:7933665
n3:druhVysledku
n13:J
n3:duvernostUdaju
n16:S
n3:entitaPredkladatele
n15:predkladatel
n3:idSjednocenehoVysledku
373
n3:idVysledku
RIV/61388980:_____/15:00439373
n3:jazykVysledku
n7:eng
n3:klicovaSlova
Corium; Fuel-Coolant Interaction; Hydrogen release; Material effect; Nuclear reactor severe accident
n3:klicoveSlovo
n4:Corium n4:Hydrogen%20release n4:Material%20effect n4:Nuclear%20reactor%20severe%20accident n4:Fuel-Coolant%20Interaction
n3:kodStatuVydavatele
GB - Spojené království Velké Británie a Severního Irska
n3:kontrolniKodProRIV
[2B5E3CA7F085]
n3:nazevZdroje
Annals of Nuclear Energy
n3:obor
n17:CA
n3:pocetDomacichTvurcuVysledku
2
n3:pocetTvurcuVysledku
7
n3:rokUplatneniVysledku
n10:2015
n3:svazekPeriodika
75
n3:tvurceVysledku
Dugne, O. Bakardjieva, Snejana Piluso, P. Bezdička, Petr Tyrpekl, J. Nižňanský, D. Rehspringer, J. L.
n3:wos
000347493400026
s:issn
0306-4549
s:numberOfPages
9
n8:doi
10.1016/j.anucene.2014.08.013