Sevecek, Martin
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Acta Polytechnica CTU Proceedings Vol. 28 (2020): ŠIMÁNĚ 2020: Student Conference on Nuclear Engineering - Articles
THERMAL ANALYSIS OF DRY STORAGE AND TRANSPORTATION CASKS CASTOR USING COBRA-SFS
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Acta Polytechnica CTU Proceedings Vol. 4 (2016): ŠIMÁNĚ 2016 - Articles
EVALUATION METRICS APPLIED TO ACCIDENT TOLERANT FUEL CLADDING CONCEPTS FOR VVER REACTORS
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Acta Polytechnica CTU Proceedings Vol. 19 (2018): ŠIMÁNĚ 2018 - Articles
STUDY OF THERMAL CREEP OF COATED CLADDING MATERIALS
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Acta Polytechnica CTU Proceedings Vol. 37 (2022): ŠIMÁNĚ 2022: Student Conference on Nuclear Engineering - Articles
Modelling of fission gas release in UO2 doped fuel using transuranus code
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Acta Polytechnica CTU Proceedings Vol. 44 (2023): Šimáně 2023 – International Conference on Nuclear Engineering - Articles
Effect of heat-treatment on material properties of L-DED printed austenistic alloy 08CH18N10T for nuclear reactor applications
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Acta Polytechnica CTU Proceedings Vol. 4 (2016): ŠIMÁNĚ 2016 - Articles
MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION
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Acta Polytechnica CTU Proceedings Vol. 14 (2018): ŠIMÁNĚ 2017 - Articles
NEUTRONIC ANALYSIS OF THE CANDIDATE MULTI-LAYER CLADDING MATERIALS WITH ENHANCED ACCIDENT TOLERANCE FOR WWER REACTORS
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Acta Polytechnica CTU Proceedings Vol. 14 (2018): ŠIMÁNĚ 2017 - Articles
IMITATING NEUTRON IRRADIATION DAMAGE USING A COMBINATION OF ION BEAMS
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Acta Polytechnica CTU Proceedings Vol. 24 (2019): ŠIMÁNĚ 2019 - Articles
HIGH-TEMPERATURE STEAM AND AIR OXIDATION OF CHROMIUM-COATED OPTIMIZED ZIRLO™
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Acta Polytechnica CTU Proceedings Vol. 14 (2018): ŠIMÁNĚ 2017 - Articles
HEAT TRANSFER MODELLING OF TWO-PHASE FLOW IN ISOLATED CHANNEL
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Acta Polytechnica CTU Proceedings Vol. 24 (2019): ŠIMÁNĚ 2019 - Articles
COATED CLADDING BEHAVIOR DURING HIGH-TEMPERATURE TRANSIENTS
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Acta Polytechnica CTU Proceedings Vol. 28 (2020): ŠIMÁNĚ 2020: Student Conference on Nuclear Engineering - Articles
HIGH-TEMPERATURE OXIDATION OF CHROME-NICKEL ALLOY
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