Search Results - "Stuckert, Juri"

An Overview of Mechanisms of the Degradation of Promising ATF Cladding Materials During Oxidation at High Temperatures by Steinbrueck, Martin, Grosse Mirco, Tang Chongchong, Stuckert Juri, Seifert, Hans Juergen

“…Accident tolerant fuel (ATF) cladding is a new type of nuclear fuel cladding designed to improve the safety and performance of nuclear reactors. In this paper,…”
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The SPIZWURZ project – Experimental investigations and modeling of the behavior of hydrogen in zirconium alloys under long-term dry storage conditions by Grosse, Mirco, Boldt, Felix, Herm, Michel, Roessger, Conrado, Stuckert, Juri, Weick, Sarah, Nahm, Daniel

“…In order to investigate the occurring processes during long-term dry storage of spent fuel assemblies, a joined project called SPIZWURZ, between the Karlsruhe…”
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Experimental and modelling results of the QUENCH-20 experiment with BWR test bundle by Stuckert, Juri, Bechta, Sevostian, Hollands, Thorsten, Isaksson, Patrick, Steinbrueck, Martin

“…•Eutectic interaction of B4C with steel blade and ZIRLO channel box at T > 1500 K.•Fast temperature escalation from 2000 to 2300 K after the reflood onset.•30%…”
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Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release by Stuckert, Juri, Steinbrueck, Martin, Kalilainen, Jarmo, Lind, Terttaliisa, Birchley, Jonathan

“…•Test with 20 el. heated, 2 unheated, 2 absorber rods under severe accident conditions.•Steam and oxygen starvation conditions.•Zirconium nitride formation and…”
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Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs by Joung, SungHoon, Kim, Jinsu, Ševeček, Martin, Stuckert, Juri, Lee, Youho

“…Post Quench Ductility (PQD) of various Cr-coated cladding designs with respect to base cladding materials, Cr coating methods, and its thickness were…”
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Preliminary validation of ASTEC V2.2.b with the QUENCH-20 BWR bundle experiment by Murat, Onur, Sanchez-Espinoza, Victor, Wang, Shisheng, Stuckert, Juri

“…•Oxidation and molten material formation during severe accident progression.•Boiling water reactors larger metallic content can produce higher hydrogen…”
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Microstructure and mechanical properties of Zircaloy-4 cladding hydrogenated at temperatures typical for loss-of-coolant accident (LOCA) conditions by Pshenichnikov, Anton, Stuckert, Juri, Walter, Mario

“…•Change of Zircaloy-4 cladding microstructure during hydriding.•Cracks origination during hydrogenation at constant temperature.•Microhardness growth from 195…”
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Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment by Doyle, Peter, Stuckert, Juri, Grosse, Mirco, Steinbrück, Martin, Nelson, Andrew T., Harp, Jason, Terrani, Kurt

“…The QUENCH-19 experiment was a first-of-its-kind full-bundle test simulating accident conditions followed by water quench on accident-tolerant fuel (ATF)…”
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Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment by Doyle, Peter, Stuckert, Juri, Grosse, Mirco, Steinbrück, Martin, Nelson, Andrew T., Harp, Jason, Terrani, Kurt

“…•The behavior of B136Y3 (FeCrAl) cladding to LOCA-type conditions was evaluated.•Hydrogen release was significantly lower than a similar test with Zr-based…”
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The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test by Kalilainen, Jarmo, Lind, Terttaliisa, Stuckert, Juri, Bergfeldt, Thomas, Sippula, Olli, Jokiniemi, Jorma

“…In this study, the aerosol release from the silver-indium-cadmium control rods during the air-ingress phase of the QUENCH-18 bundle test was investigated both…”
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Hydride precipitation, fracture and plasticity mechanisms in pure zirconium and Zircaloy-4 at temperatures typical for the postulated loss-of-coolant accident by Pshenichnikov, Anton, Stuckert, Juri, Walter, Mario

“…•All δ-hydrides in Zr and Zircaloy-4 have basal or pyramidal types of habit planes.•Seven orientation relationships for δ-hydrides in Zr matrix were…”
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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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Hafnium oxidation at high temperature in steam by Guilbert-Banti, S., Viretto, A., Barrachin, M., Tanguy, C., Steinbrück, M., Stuckert, J.

“…To assess the potential impact of using hafnium as absorber material in LWRs in high temperature accidental situations, the oxidation behavior of hafnium was…”
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Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation by Große, Mirco, Lehmann, Eberhard, Steinbrück, Martin, Kühne, Guido, Stuckert, Juri

“…The influence of the oxide layer morphology on the hydrogen uptake during steam oxidation of (Zr,Sn) and Zr–Nb nuclear fuel rod cladding alloys was…”
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Secondary hydriding during LOCA – Results from the QUENCH-L0 test by Grosse, Mirco, Stuckert, Juri, Steinbrück, Martin, Kaestner, Anders

“…A shortened loss of coolant scenario was simulated experimentally at fuel rod bundle scale in the QUENCH-L0 test. All pressurized specimens burst at…”
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Application of neutron radiography to study material processes during hypothetical severe accidents in nuclear reactors by Große, Mirco, Steinbrück, Martin, Stuckert, Juri, Kastner, Anders, Schillinger, Burkhard

“…Neutron radiography was applied for investigations of nuclear fuel cladding and control rod behaviour during steam oxidation at temperatures between 1123 and…”
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Validation of ASTECV2.1 based on the QUENCH-08 experiment by Gómez-García-Toraño, Ignacio, Sánchez-Espinoza, Víctor-Hugo, Stieglitz, Robert, Stuckert, Juri, Laborde, Laurent, Belon, Sébastien

“…•ASTECV2.1 can reproduce QUENCH-08 experimental trends e.g. hydrogen generation.•Radial temperature gradient and heat transfer through argon gap are…”
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Land contamination activity data interpretation from Fukushima Daiichi accident by Jäckel, Bernd S., Bevilacqua, Arturo, Ducros, Gerard, Gauntt, Randall, Stuckert, Juri

“…•Radiochemical analysis of activity sources from land contamination.•Calculation of activity release from unit 3.•Analysis of origin of land contamination from…”
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On the EU-Japan roadmap for experimental research on corium behavior by Bechta, Sevostian, Ma, Weimin, Miassoedov, Alexei, Journeau, Christophe, Okamoto, Koji, Manara, Dario, Bottomley, David, Kurata, Masaki, Sehgal, Bal Raj, Stuckert, Juri, Steinbrueck, Martin, Fluhrer, Beatrix, Keim, Torsten, Fischer, Manfred, Langrock, Gert, Piluso, Pascal, Hozer, Zoltan, Kiselova, Monika, Belloni, Francesco, Schyns, Marc

“…•A review of ongoing severe accident studies on corium behavior was presented.•A comparison of research priorities identified in different projects was…”
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SARNET2 benchmark on air ingress experiments QUENCH-10, -16 by Fernandez-Moguel, Leticia, Bals, Christine, Beuzet, Emilie, Bratfisch, Christian, Coindreau, Olivia, Hózer, Zoltan, Stuckert, Juri, Vasiliev, Alexander, Vryashkova, Petya

“…•Two similar QUENCH air ingress experiments were analysed with eight different codes.•Eight institutions have participated in the study.•Differences in the…”
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