Hasil Pencarian - Martin Sevecek

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  1. 1
    MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION

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

    Diterbitkan 2016-12-01
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  2. 2
    Modelling of fission gas release in UO2 doped fuel using transuranus code

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

    Diterbitkan 2022-12-01
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  3. 3
    EVALUATION METRICS APPLIED TO ACCIDENT TOLERANT FUEL CLADDING CONCEPTS FOR VVER REACTORS

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

    Diterbitkan 2016-12-01
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  4. 4
    NEUTRONIC ANALYSIS OF THE CANDIDATE MULTI-LAYER CLADDING MATERIALS WITH ENHANCED ACCIDENT TOLERANCE FOR WWER REACTORS

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

    Diterbitkan 2018-05-01
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  5. 5
    IMITATING NEUTRON IRRADIATION DAMAGE USING A COMBINATION OF ION BEAMS

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

    Diterbitkan 2018-05-01
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  6. 6
    HEAT TRANSFER MODELLING OF TWO-PHASE FLOW IN ISOLATED CHANNEL

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

    Diterbitkan 2018-05-01
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  7. 7
    STUDY OF THERMAL CREEP OF COATED CLADDING MATERIALS

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

    Diterbitkan 2018-12-01
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  8. 8
    THERMAL ANALYSIS OF DRY STORAGE AND TRANSPORTATION CASKS CASTOR USING COBRA-SFS

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

    Diterbitkan 2020-12-01
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  9. 9
    Geometry Optimization of Dispersed UMo Fuel for Light Water Reactors

    Geometry Optimization of Dispersed UMo Fuel for Light Water Reactors oleh Ondrej Novak, Pavel Suk, Dusan Kobylka, Martin Sevecek

    Diterbitkan 2023-09-01
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  10. 10
    HIGH-TEMPERATURE STEAM AND AIR OXIDATION OF CHROMIUM-COATED OPTIMIZED ZIRLO™

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

    Diterbitkan 2019-12-01
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  11. 11
    Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment

    Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment oleh Tereza Abrman Marková, Guglielmo Lomonaco, Guido Mazzini, Martin Ševeček

    Diterbitkan 2023-03-01
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  12. 12
    HIGH-TEMPERATURE OXIDATION OF CHROME-NICKEL ALLOY

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

    Diterbitkan 2020-12-01
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  13. 13
    Effect of heat-treatment on material properties of L-DED printed austenistic alloy 08CH18N10T for nuclear reactor applications

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

    Diterbitkan 2023-12-01
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  14. 14
    Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance

    Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance oleh Martin Ševeček, Anil Gurgen, Arunkumar Seshadri, Yifeng Che, Malik Wagih, Bren Phillips, Victor Champagne, Koroush Shirvan

    Diterbitkan 2018-03-01
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  15. 15
    COATED CLADDING BEHAVIOR DURING HIGH-TEMPERATURE TRANSIENTS

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

    Diterbitkan 2019-12-01
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  16. 16
    Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes

    Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes oleh David Kamerman, Fabiola Cappia, Katelyn Wheeler, Philip Petersen, Erik Rosvall, Tyler Dabney, Hwasung Yeom, Kumar Sridharan, Martin Ševeček, Jason Schulthess

    Diterbitkan 2022-06-01
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  17. 17
    Development and testing of multicomponent fuel cladding with enhanced accidental performance

    Development and testing of multicomponent fuel cladding with enhanced accidental performance oleh Jakub Krejčí, Jitka Kabátová, František Manoch, Jan Kočí, Ladislav Cvrček, Jaroslav Málek, Stanislav Krum, Pavel Šutta, Petra Bublíková, Patricie Halodová, Hygreeva Kiran Namburi, Martin Ševeček

    Diterbitkan 2020-03-01
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