Search Results - "Nóra, Vér"

Segmented mandrel tests of as-received and hydrogenated WWER fuel cladding tubes by Király, Márton, Horváth, Márta, Nagy, Richárd, Vér, Nóra, Hózer, Zoltán

“…The mechanical interaction between the fuel pellet and the cladding tube of a nuclear fuel rod is a very important for safety studies as this phenomenon could…”
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Predicting the uptake of Cs, Co, Ni, Eu, Th and U on argillaceous rocks using sorption models for illite by Marques Fernandes, Maria, Vér, Nóra, Baeyens, Bart

“…•Contaminant retention in argillaceous rocks controlled by sorption on clay minerals.•Cs, Ni, Co, Eu, Th and UO2 sorption isotherm measurements on Boda and…”
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Effect of steam and oxygen starvation on severe accident progression with air ingress by Farkas, Róbert, Hózer, Zoltán, Nagy, Imre, Vér, Nóra, Horváth, Márta, Steinbrück, Martin, Stuckert, Juri, Grosse, Mirco

“…•Severe accident air ingress scenario was simulated with electrically heated fuel bundle.•Strong oxidation and nitriding resulted in complex microstructure in…”
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Experimental simulation of selected design extension condition scenarios without core meltdown in the CODEX facility by Farkas, Róbert, Hózer, Zoltán, Nagy, Imre, Vér, Nóra, Szabó, Péter, Horváth, Márta, Kostka, Pál, Lajtha, Gábor

“…Two DEC-A scenarios were simulated with electrically heated 7-rod bundles. The test parameters were selected on the basis of reference scenarios from VVER-440…”
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Experimental investigation of the coolability of blocked hexagonal bundles by Hózer, Zoltán, Nagy, Imre, Kunstár, Mihály, Szabó, Péter, Vér, Nóra, Farkas, Róbert, Trosztel, István, Vimi, András

“…•Experiments were performed with electrically heated hexagonal fuel bundles.•Coolability of ballooned VVER-440 type bundle was confirmed up to high blockage…”
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Ruténium viselkedése levegıbetöréses reaktorbaleset során by Nóra, Vér

“…A RUSET program célja egy levegıbetöréses súlyos reaktorbaleset során a ruténiumoxidok lehetséges viselkedésének tisztázása volt. A kísérletek elsısorban a…”
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Oxidation of Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600–1200 °C by STEINBRÜCK, Martin, VER, Nóra, GROSSE, Mirco

“…The oxidation kinetics of the classical pressurized water reactors (PWR) cladding alloy Zircaloy-4 have been extensively investigated over a wide temperature…”
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Quenching of high temperature VVER fuel after long term oxidation in hydrogen rich steam by Hózer, Zoltán, Balaskó, Márton, Horváth, Márta, Kunstár, Mihály, Matus, Lajos, Nagy, Imre, Novotny, Tamás, Perez-Feró, Erzsébet, Pintér, Anna, Vér, Nóra, Vimi, András, Windberg, Péter

“…A cleaning tank incident at Paks NPP resulted in severe fuel damage of thirty VVER-440 type assemblies. The fuel rods heated up due to insufficient cooling and…”
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