| Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance M Ševeček, A Gurgen, A Seshadri, Y Che, M Wagih, B Phillips, ... Nuclear Engineering and Technology 50 (2), 229-236, 2018 | 163 | 2018 |
| Development and testing of multicomponent fuel cladding with enhanced accidental performance J Krejčí, J Kabátová, F Manoch, J Kočí, L Cvrček, J Málek, S Krum, P Šutta, ... Nuclear Engineering and Technology 52 (3), 597-609, 2020 | 86 | 2020 |
| State-of-the-art report on light water reactor accident-tolerant fuels K Pasamehmetoglu, S Massara, D Costa, S Bragg-Sitton, M Moatti, ... Organisation for Economic Co-Operation and Development, 2018 | 40 | 2018 |
| Quenching heat transfer analysis of accident tolerant coated fuel cladding A Seshadri, K Shirvan Nuclear Engineering and Design 338, 5-15, 2018 | 34 | 2018 |
| Experimental behavior of chromium-based coatings J Krejčí, M Ševeček, J Kabátová, F Manoch, J Kočí, L Cvrček, J Málek, ... Proceedings of the TopFuel, A0233, 2018 | 32 | 2018 |
| Study on neutronics of VVER-1200 with accident tolerant fuel cladding F Fejt, M Sevecek, J Frybort, O Novak Annals of Nuclear Energy 124, 579-591, 2019 | 26 | 2019 |
| Fatigue behavior of cold spray-coated accident tolerant cladding M Ševeček, J Krejčí, MH Shahin, J Petrik, RG Ballinger, K Shirvan Proceedings of the TopFuel, 2018 | 18 | 2018 |
| Chromium and chromium nitride coated cladding for nuclear reactor fuel J Krejčí, M Ševeček, L Cvrček, J Kabátová, F Manoch Proceedings of the 20th International Corrosion Congress, EUROCORR 2017, 2017 | 17 | 2017 |
| Development of chromium and chromium nitride coated cladding for VVER reactors J Krejci, M Sevecek, L Cvrcek 2017 WRFPM, 2017 | 16 | 2017 |
| Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes D Kamerman, F Cappia, K Wheeler, P Petersen, E Rosvall, T Dabney, ... Nuclear Materials and Energy 31, 101175, 2022 | 10 | 2022 |
| P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments V D’Ambrosi, J Sercombe, S Bejaoui, A Chaieb, B Baurens, R Largenton, ... Nuclear Technology 210 (2), 189-215, 2024 | 9 | 2024 |
| Evaluation Metrics Applied to Accident Tolerant Fuel Cladding Concepts for VVER Reactors M Sevecek, M Valach Acta Polytechnica CTU Proceedings 4, 89-96, 2016 | 9 | 2016 |
| Coated cladding behavior during high-temperature transients A Chalupová, J Krejčí, L Cvrček, M Ševeček, V Rozkošný, A Přibyl, ... České vysoké učení technické v Praze, 2019 | 8 | 2019 |
| Neutronic analysis of the candidate multi-layer cladding materials with enhanced accident tolerance for wwer reactors O Novák, M Ševeček Acta Polytechnica CTU Proceedings 14, 27-33, 2018 | 8 | 2018 |
| Characterization of eutectic reaction of Cr and Cr/CrN coated zircaloy accident tolerant fuel cladding D Kim, M Ševeček, Y Lee Nuclear Engineering and Technology 55 (10), 3535-3542, 2023 | 6 | 2023 |
| Neutronic performance of VVER-1200 reactor with advanced fuel and cladding materials P Suk, M Ševeček, D Kobylka, F Fejt Nuclear Engineering and Design 405, 112216, 2023 | 5 | 2023 |
| Experimental investigation of cold-spray Cr-coated cladding during normal and accident conditions K Shirvan, A Seshadri, A Dave, B Philips, M Ševeček, J Krejčí, ... 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light …, 2020 | 5 | 2020 |
| Microstructure of zirconium fuel claddings: TEM and EBSD studies of as-received and neutron-irradiated materials P Gávelová, P Halodová, B Křivská, CA Correa, J Krejčí, M Ševeček, ... Manufacturing Technology 20 (6), 720-727, 2020 | 5 | 2020 |
| High-temperature steam and air oxidation of chromium-coated optimized ZIRLO™ G Bourdon, M Ševecek, J Krejčí, L Cvrček České vysoké učení technické v Praze, 2019 | 5 | 2019 |
| Development of high thermal conductivity UO2–Th heterogeneous fuel M Ševeček, J Kubáň, M Valach, R Škoda Progress in Nuclear Energy 108, 489-496, 2018 | 4 | 2018 |
Koroush ShirvanProfessor of Nuclear Engineering, MITE-mailová adresa ověřena na: mit.edu
