Krejčí, Jakub
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Acta Polytechnica CTU Proceedings Vol. 4 (2016): ŠIMÁNĚ 2016 - Articles
HYDROGEN CHARGING OF FUEL CLADDING METHODOLOGY
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Acta Polytechnica CTU Proceedings Vol. 28 (2020): ŠIMÁNĚ 2020: Student Conference on Nuclear Engineering - Articles
EXPERIMENTAL STUDY OF DAMAGED CR-COATED FUEL CLADDING IN POST-ACCIDENT CONDITIONS
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Acta Polytechnica CTU Proceedings Vol. 37 (2022): ŠIMÁNĚ 2022: Student Conference on Nuclear Engineering - Articles
Degradation of Cr-coated cladding under the simulated Loss-of-Coolant Accident phenomena
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Acta Polytechnica CTU Proceedings Vol. 4 (2016): ŠIMÁNĚ 2016 - Articles
POST CRITICAL HEAT TRANSFER AND FUEL CLADDING OXIDATION
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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. 44 (2023): Šimáně 2023 – International Conference on Nuclear Engineering - Articles
Simulation of the compression test of the Zr1Nb fuel cladding ring
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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. 28 (2020): ŠIMÁNĚ 2020: Student Conference on Nuclear Engineering - Articles
HIGH-TEMPERATURE OXIDATION OF CHROME-NICKEL ALLOY
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Acta Polytechnica CTU Proceedings Vol. 24 (2019): ŠIMÁNĚ 2019 - Articles
DEBRIS-FRETTING TEST OF COATED AND UNCOATED ZR-1%NB CLADDING
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Acta Polytechnica CTU Proceedings Vol. 27 (2020): Proceedings of the 14th International Conference on Local Mechanical Properties - LMP 2019 - Articles
NANOINDENTATION OF HYDROGEN ENRICHED Zr-1Nb ZIRCONIUM ALLOY NUCLEAR FUEL CLADDINGS
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