MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION by Miroslav Cech, Martin Sevecek

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Modelling of fission gas release in UO2 doped fuel using transuranus code by Jheffry Gonzalez, Martin Ševecek

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EVALUATION METRICS APPLIED TO ACCIDENT TOLERANT FUEL CLADDING CONCEPTS FOR VVER REACTORS by Martin Sevecek, Mojmir Valach

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NEUTRONIC ANALYSIS OF THE CANDIDATE MULTI-LAYER CLADDING MATERIALS WITH ENHANCED ACCIDENT TOLERANCE FOR WWER REACTORS by Ondřej Novák, Martin Ševeček

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IMITATING NEUTRON IRRADIATION DAMAGE USING A COMBINATION OF ION BEAMS by Václav Šísl, Martin Ševeček

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HEAT TRANSFER MODELLING OF TWO-PHASE FLOW IN ISOLATED CHANNEL by Daniel Vlček, Vojtěch Caha, Martin Ševeček

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STUDY OF THERMAL CREEP OF COATED CLADDING MATERIALS by Martin Ševeček, Koroush Shirvan, Ronald G. Ballinger

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THERMAL ANALYSIS OF DRY STORAGE AND TRANSPORTATION CASKS CASTOR USING COBRA-SFS by Martin Ševeček, Mojmír Valach, Chih-Hao Lee

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HIGH-TEMPERATURE STEAM AND AIR OXIDATION OF CHROMIUM-COATED OPTIMIZED ZIRLO™ by Gauthier Bourdon, Martin Ševecek, Jakub Krejčí, Ladislav Cvrček

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HIGH-TEMPERATURE OXIDATION OF CHROME-NICKEL ALLOY by Adéla Chalupová, Martin Steinbrück, Mirco Grosse, Jakub Krejčí, Martin Ševeček

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Effect of heat-treatment on material properties of L-DED printed austenistic alloy 08CH18N10T for nuclear reactor applications by Štěpán Jedlan, Martin Ševeček, Antonín Prantl, Josef Hodek, Pavel Podaný, Michal Brázda

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COATED CLADDING BEHAVIOR DURING HIGH-TEMPERATURE TRANSIENTS by Adéla Chalupová, Jakub Krejčí, Ladislav Cvrček, Martin Ševeček, Vojtěch Rozkošný, Antonín Přibyl, Patricie Halodová, Petra Gávelová

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Micro-mechanical evaluations of adhesion properties for Cr-coated accident tolerant fuel cladding by Jong-Dae Hong, Hongryul Oh, Daehyeok Ahn, Dongchan Jang, Hyun-Gil Kim, JaeYong Kim, Hyochan Kim, Martin Ševeček

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