| Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings C Tang, M Stueber, HJ Seifert, M Steinbrueck Corrosion reviews 35 (3), 141-165, 2017 | 406 | 2017 |
| Review on chromium coated zirconium alloy accident tolerant fuel cladding J Yang, M Steinbrück, C Tang, M Große, J Liu, J Zhang, D Yun, S Wang Journal of Alloys and Compounds 895, 162450, 2022 | 178 | 2022 |
| Air oxidation of Zircaloy-4, M5® and ZIRLO™ cladding alloys at high temperatures M Steinbrück, M Böttcher Journal of Nuclear Materials 414 (2), 276-285, 2011 | 177 | 2011 |
| Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures M Steinbrück Journal of Nuclear Materials 392 (3), 531-544, 2009 | 164 | 2009 |
| Synopsis and outcome of the QUENCH experimental program M Steinbrück, M Große, L Sepold, J Stuckert Nuclear Engineering and Design 240 (7), 1714-1727, 2010 | 163 | 2010 |
| Oxidation of advanced zirconium cladding alloys in steam at temperatures in the range of 600–1200 C M Steinbrück, N Vér, M Große Oxidation of metals 76, 215-232, 2011 | 146 | 2011 |
| Oxidation kinetics of Cr-coated zirconium alloy: Effect of coating thickness and microstructure EB Kashkarov, DV Sidelev, MS Syrtanov, C Tang, M Steinbrück Corrosion Science 175, 108883, 2020 | 123 | 2020 |
| Hydrogen absorption by zirconium alloys at high temperatures M Steinbrück Journal of nuclear materials 334 (1), 58-64, 2004 | 117 | 2004 |
| High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment J Yang, U Stegmaier, C Tang, M Steinbrück, M Große, S Wang, HJ Seifert Journal of Nuclear Materials 547, 152806, 2021 | 110 | 2021 |
| Deposition, characterization and high-temperature steam oxidation behavior of single-phase Ti2AlC-coated Zircaloy-4 C Tang, M Steinbrueck, M Stueber, M Grosse, X Yu, S Ulrich, HJ Seifert Corrosion science 135, 87-98, 2018 | 102 | 2018 |
| Oxidation of boron carbide at high temperatures M Steinbrück Journal of Nuclear Materials 336 (2-3), 185-193, 2005 | 98 | 2005 |
| Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation M Große, E Lehmann, M Steinbrück, G Kühne, J Stuckert Journal of Nuclear Materials 385 (2), 339-345, 2009 | 91 | 2009 |
| Degradation and oxidation of B4C control rod segments at high temperatures M Steinbrück Journal of Nuclear Materials 400 (2), 138-150, 2010 | 89 | 2010 |
| Separate-effect tests on zirconium cladding degradation in air ingress situations C Duriez, M Steinbrück, D Ohai, T Meleg, J Birchley, T Haste Nuclear Engineering and Design 239 (2), 244-253, 2009 | 87 | 2009 |
| Core loss during a severe accident (COLOSS) B Adroguer, F Bertrand, P Chatelard, N Cocuaud, JP Van Dorsselaere, ... Nuclear Engineering and Design 235 (2-4), 173-198, 2005 | 85 | 2005 |
| Synthesis and characterization of Ti2AlC coatings by magnetron sputtering from three elemental targets and ex-situ annealing C Tang, M Klimenkov, U Jaentsch, H Leiste, M Rinke, S Ulrich, ... Surface and Coatings Technology 309, 445-455, 2017 | 83 | 2017 |
| Oxidation at high temperatures in steam atmosphere and quench of silicon carbide composites for nuclear application VA Avincola, M Grosse, U Stegmaier, M Steinbrueck, HJ Seifert Nuclear Engineering and Design 295, 468-478, 2015 | 81 | 2015 |
| High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys M Steinbrück, J Birchley, AV Boldyrev, AV Goryachev, M Grosse, TJ Haste, ... Progress in Nuclear Energy 52 (1), 19-36, 2010 | 81 | 2010 |
| Oxidation of Zircaloy-4 in steam-nitrogen mixtures at 600–1200 C M Steinbrueck, FO da Silva, M Grosse Journal of Nuclear Materials 490, 226-237, 2017 | 79 | 2017 |
| Transient experiments on oxidation and degradation of Cr-coated Zircaloy in steam up to 1600℃ J Liu, C Tang, M Steinbrück, J Yang, U Stegmaier, M Große, D Yun, ... Corrosion Science 192, 109805, 2021 | 73 | 2021 |
Mikhail VESHCHUNOVNuclear Safety Institute (IBRAE), Russian Academy of Science在 ibrae.ac.ru 的电子邮件经过验证
