Comparative study on thermal creep resistance of arc ion plated and magnetron sputtered Cr coatings on Zircaloy-4 cladding for accident tolerant fuel
Year of publication
2026
Publication
Nuclear Engineering and Technology. 2026, 58(5), ISSN 1738-5733.
Side-by-side high-temperature accident performance of ATF and conventional claddings in the CODEX-ATF experiment
Year of publication
2026
Publication
Nuclear Engineering and Design. 2026, 450 ISSN 0029-5493.
High-temperature creep behavior of Cr-coated optimized ZIRLO™ cladding via inverse analysis based on finite element method
Year of publication
2025
Publication
Nuclear Engineering and Design. 2025, 444 ISSN 0029-5493.
Investigation of the temperature-dependent failure processes in PVD Cr-coated ZIRLO nuclear fuel cladding using in situ X-ray micro-tomography imaging
Year of publication
2025
Publication
Surface & Coatings Technology. 2025, 512 ISSN 0257-8972.
Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs
Year of publication
2024
Publication
Journal of Nuclear Materials. 2024, 591 1-15. ISSN 0022-3115.
Micro-mechanical evaluations of adhesion properties for Cr-coated accident tolerant fuel cladding
Year of publication
2024
Publication
Nuclear Materials and Energy. 2024, 41 ISSN 2352-1791.
Analyses of design extension conditions without significant fuel degradation for operating nuclear power plants: An OECD/NEA review
Year of publication
2024
Publication
Nuclear Engineering and Design. 2024, 425(425), ISSN 0029-5493.
Contribution of IAEA coordinated research projects to light water reactors advanced technology fuel testing and simulation
Year of publication
2024
Publication
Nuclear Engineering and Design. 2024, 418 ISSN 0029-5493.
Neutronic performance of VVER-1200 reactor with advanced fuel and cladding materials
Year of publication
2023
Publication
Nuclear Engineering and Design. 2023, 405 ISSN 1872-759X.
Measurement of local mechanical properties for Cr-coated accident tolerant fuel cladding
Year of publication
2023
Publication
Journal of Nuclear Materials. 2023, 579 ISSN 1873-4820.
Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment
Year of publication
2023
Publication
Energies. 2023, 16(6), ISSN 1996-1073.
Geometry Optimization of Dispersed U-Mo Fuel for Light Water Reactors
Year of publication
2023
Publication
Nuclear Engineering and Technology. 2023, 55(9), 3464-3471. ISSN 1738-5733.
Characterization of eutectic reaction of Cr and Cr/CrN coated zircaloy accident tolerant fuel cladding
Year of publication
2023
Publication
Nuclear Engineering and Technology. 2023, 55(10), 3535-3542. ISSN 1738-5733.
Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes
Year of publication
2022
Publication
Nuclear Materials and Energy. 2022, 21(101175), ISSN 2352-1791.
High-temperature oxidation of chrome-nickel alloy
Year of publication
2020
Publication
Acta Polytechnica CTU Proceedings. 2020, 28 8-14. ISSN 2336-5382.
Thermal analysis of dry storage and transportation casks castor using COBRA-SFS
Year of publication
2020
Publication
Acta Polytechnica CTU Proceedings. 2020, 28 32-41. ISSN 2336-5382.
Development and testing of multicomponent fuel cladding with enhanced accidental performance
Year of publication
2020
Publication
Nuclear Engineering and Technology. 2020, 52(3), 597-609. ISSN 1738-5733.
Study on Neutronics of VVER-1200 with Accident Tolerant Fuel Cladding
Year of publication
2019
Publication
Annals of Nuclear Energy. 2019, 124 579-591. ISSN 0306-4549.
Development of high thermal conductivity UO2–Th heterogeneous fuel
Year of publication
2018
Publication
Progress in Nuclear Energy. 2018, 108 489-496. ISSN 0149-1970.
Development of Cr Cold-Spray Coated Fuel Cladding with Enhanced Accident Tolerance
Year of publication
2018
Publication
Nuclear Engineering and Technology. 2018, 50(2), 229-236. ISSN 1738-5733.