Publikationsliste


An Overview of Mechanisms of the Degradation of Promising ATF Cladding Materials During Oxidation at High Temperatures
Steinbrueck, M.; Grosse, M.; Tang, C.; Stuckert, J.; Seifert, H. J.
2024. High Temperature Corrosion of Materials. doi:10.1007/s11085-024-10229-y
Corrosion behavior of various conductive materials in Sb3Sn7 alloy at 450 °C
Zhang, T.; Fetzer, R.; Heinzel, A.; Weisenburger, A.; Tang, C.; Stüber, M.; Müller, G.
2024. Corrosion Science, 227, Article no: 111797. doi:10.1016/j.corsci.2023.111797
Eutectic reaction and oxidation behavior of Cr-coated Zircaloy-4 accident-tolerant fuel cladding under various heating rates
Kim, D.; Steinbrück, M.; Große, M.; Tang, C.; Lee, Y.
2023. Journal of Nuclear Materials, 583, Art.-Nr.: 154538. doi:10.1016/j.jnucmat.2023.154538
Synthesis of VAlC thin films by thermal annealing of nanoscale elemental multilayered precursors: Incorporation of layered Ar bubbles and impact on microstructure formation
Tang, C.; Dürrschnabel, M.; Jäntsch, U.; Klimenkov, M.; Steinbrück, M.; Ulrich, S.; Hans, M.; Schneider, J. M.; Stüber, M.
2023. Applied Surface Science, 629, Art.-Nr.: 157340. doi:10.1016/j.apsusc.2023.157340
Limiting degradation mechanisms for high-temperature oxidation resistance of promising ATF cladding solutions
Steinbrück, M.; Große, M.; Tang, C.; Stuckert, J.
2022. Proceedings | TopFuel 2022 Light Water Reactor Fuel Performance Conference | Raleigh, NC, October 9-13, 2022, 251–260, American Nuclear Society (ANS). doi:10.13182/TopFuel22-38967
Phase formation and thermal stability of quaternary MAX phase thin films in the Cr-V-C-Al system: an experimental combinatorial study
Tang, C.; Dürrschnabel, M.; Jäntsch, U.; Klimenkov, M.; Steinbrück, M.; Ulrich, S.; Hans, M.; Schneider, J. M.; Stüber, M.
2022, Oktober 19. 4th International Conference on Materials: Advanced and Emerging Materials (2022), Barcelona, Spanien, 19.–21. Oktober 2022
Microstructural evolution of pre-oxidized Cr-coated Zry-4 during annealing in argon
Liu, J.; Meng, R.; Steinbrück, M.; Große, M.; Stegmaier, U.; Tang, C.; Yang, J.; Yun, D.
2023. Journal of Nuclear Materials, 573, Art.-Nr.: 154144. doi:10.1016/j.jnucmat.2022.154144
Influence of coating parameters on oxidation behavior of Cr-coated zirconium alloy for accident tolerant fuel claddings
Kashkarov, E. B.; Sidelev, D. V.; Pushilina, N. S.; Yang, J.; Tang, C.; Steinbrueck, M.
2022. Corrosion Science, 203, Article no: 110359. doi:10.1016/j.corsci.2022.110359
Systematic investigations on the coating degradation mechanism during the steam oxidation of Cr-coated Zry-4 at 1200 °C
Liu, J.; Steinbrück, M.; Große, M.; Stegmaier, U.; Tang, C.; Yun, D.; Yang, J.; Cui, Y.; Seifert, H. J.
2022. Corrosion Science, 202, Art.-Nr.: 110310. doi:10.1016/j.corsci.2022.110310
Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500–1500 °C in steam
Kim, C.; Tang, C.; Grosse, M.; Maeng, Y.; Jang, C.; Steinbrueck, M.
2022. Journal of Nuclear Materials, 564, Art.-Nr.: 153696. doi:10.1016/j.jnucmat.2022.153696
Oxidation kinetics of nuclear-grade FeCrAl alloys in steam in the temperature range 600-1500°C
Kim, C.; Tang, C.; Große, M.; Steinbrück, M.
2021. Proceedings of TOPFUEL 2021 Conference
Review on chromium coated zirconium alloy accident tolerant fuel cladding
Yang, J.; Steinbrück, M.; Tang, C.; Große, M.; Liu, J.; Zhang, J.; Yun, D.; Wang, S.
2022. Journal of Alloys and Compounds, 895, Art.Nr. 162450. doi:10.1016/j.jallcom.2021.162450
High-temperature oxidation of AlCrFeNi-(Mn or Co) high-entropy alloys: Effect of atmosphere and reactive element addition
Tang, C.; Shi, H.; Jianu, A.; Weisenburger, A.; Victor, G.; Grosse, M.; Müller, G.; Seifert, H. J.; Steinbrück, M.
2021. Corrosion science, 192, Art.Nr.: 109809. doi:10.1016/j.corsci.2021.109809
Transient experiments on oxidation and degradation of Cr-coated Zircaloy in steam up to 1600 ℃
Liu, J.; Tang, C.; Steinbrück, M.; Yang, J.; Stegmaier, U.; Große, M.; Yun, D.; Seifert, H. J.
2021. Corrosion science, 192, Art.-Nr.: 109805. doi:10.1016/j.corsci.2021.109805
High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment
Yang, J.; Stegmaier, U.; Tang, C.; Steinbrück, M.; Große, M.; Wang, S.; Seifert, H. J.
2021. Journal of nuclear materials, 547, Art.-Nr. 152806. doi:10.1016/j.jnucmat.2021.152806
High-temperature oxidation and hydrothermal corrosion of textured CrAlC-based coatings on zirconium alloy fuel cladding
Tang, C.; Große, M.; Ulrich, S.; Klimenkov, M.; Jäntsch, U.; Seifert, H. J.; Stüber, M.; Steinbrück, M.
2021. Surface and Coatings Technology, 419, Art.-Nr.: 127263. doi:10.1016/j.surfcoat.2021.127263
Development of Cr-C-Al based coatings for enhanced accident tolerant fuel (ATF) zirconium-based alloy cladding
Tang, C.; Grosse, M.; Steinbrück, M.; Ulrich, S.; Seifert, H. J.; Stüber, M.
2021. TopFuel (2021), Santander, Spanien, 24.–28. Oktober 2021
Metallic and Ceramic Coatings for Enhanced Accident Tolerant Fuel Cladding
Tang, C.; Stüber, M.; Seifert, H. J.; Steinbrück, M.
2020. Comprehensive Nuclear Materials. Ed.: R.J.M. Konings. Vol. 4, 490–514, Elsevier. doi:10.1016/b978-0-12-803581-8.11625-x
Oxidation kinetics of Cr-coated zirconium alloy: Effect of coating thickness and microstructure
Kashkarov, E. B.; Sidelev, D. V.; Syrtanov, M. S.; Tang, C.; Steinbrück, M.
2020. Corrosion science, 175, 108883. doi:10.1016/j.corsci.2020.108883
Oxidation behavior and microstructure evolution of alumina-forming austenitic & high entropy alloys in steam environment at 1200 °C
Shi, H.; Tang, C.; Jianu, A.; Fetzer, R.; Weisenburger, A.; Steinbrueck, M.; Grosse, M.; Stieglitz, R.; Müller, G.
2020. Corrosion science, 170, Article: 108654. doi:10.1016/j.corsci.2020.108654
Round robin exercise of the candidate ATF cladding materials within the IAEA ACTOF project
Ševeček, M.; Krejčí, J.; Chalupová, A.; Kabátová, J.; Manoch, F.; Kočí, J.; Cvrček, L.; Tang, C.; Steinbrűck, M.; Grosse, M.; Penttilä, S.; Autio, J.-M.; Lydman, J.; Toivonen, A.; Sartowska, B.; Starosta, W.; Waliś, L.; Hózer, Z.; Novotny, T.; Perezné-Feró, E.; Csordás, A. P.; Horváth, M.; Szabó, P.; Giovedi, C.; Xu, P.
2020. International Nuclear Fuel Cycle Conference, GLOBAL 2019: Seattle, WA, USA, 22–27 September 2019, 283–290, ANS
Investigation of corrosion and high temperature oxidation of promising ATF cladding materials in the framework of the Il trovatore project
Grosse, M. M.; Loo, K. van; Frankberg, E. L.; Tang, C.; Lambrinou, K.; Di Fonzo, F.; Steinbrück, M.
2020. International Nuclear Fuel Cycle Conference, GLOBAL 2019: Seattle, WA, USA, 22–27 September 2019, 274–279, American Nuclear Society (ANS)
Oxidation and Quench Behavior of Cold Spraying Cr-Coated Zircaloy Fuel Cladding Under Severe Accident Scenarios [in press]
Tang, C.; Grosse, M.; Martin Steinbrueck; Shirvan, K.
2019. TopFuel 2019, 855–863
Round Robin Exercise of the Candidate ATF Cladding Materials Within the ACTOF Project [in press]
Ševeček, M.; Krejčí, J.; Chalupová, A.; Kabátová, J.; Manoch, F.; Kočí, J.; Cvrček, L.; Tang, C.; Steinbrűck, M.; Grosse, M.; Penttilä, S.; Autio, J.-M.; Lydman, J.; Toivonen, A.; Sartowska, B.; Starosta, W.; Waliś, L.; Hózer, Z.; Novotny, T.; Perezné-Feró, E.; Pintér Csordás, A.; Horváth, M.; Szabó, P.; Giovedi, C.; Xu, P.
2019. Top Fuel 2019, American Nuclear Society, Seattle, WA, September, 22-26, 283–290, Greyden Press
Corrosion resistance and microstructural stability of austenitic Fe–Cr–Al–Ni model alloys exposed to oxygen-containing molten lead
Shi, H.; Jianu, A.; Weisenburger, A.; Tang, C.; Heinzel, A.; Fetzer, R.; Lang, F.; Stieglitz, R.; Müller, G.
2019. Journal of nuclear materials, 524, 177–190. doi:10.1016/j.jnucmat.2019.06.043
Magnetron-sputtered Al-containing MAX phase carbide thin films and their application as oxidation-resistant coatings
Tang, C.; Steinbrück, M.; Grosse, M.; Sven Ulrich; Stueber, M.; Seifert, H. J.
2018, September 28. Materials Science and Engineering Congress (MSE 2018), Darmstadt, Deutschland, 26.–28. September 2018
Evaluation of Magnetron sputtered protective ZR-C-AL coatings for accident tolerant zircaloy claddings
Tang, C.; Steinbrueck, M.; Grosse, M.; Ulrich, S.; Stueber, M.; Seifert, H. J.
2017. Water Reactor Fuel Performance Meeting (WRFPM), September 10-14, 2017, Jeju Island, Korea, 1–9
H₂ permeation behavior of Cr₂AlC and Ti₂AlC max phase coated zircaloy-4 by neutron radiography
Tang, C.; Grosse, M.; Trtik, P.; Steinbrueck, M.; Stueber, M.; Seifert, H. J.
2018. Acta polytechnica, 58 (1), 69–76. doi:10.14311/AP.2018.58.0069
High-temperature oxidation resistance and self-healing behavior of Cr2AlC MAX phase coating on Zircaloy-4
Tang, C.; Steinbrueck, M.; Grosse, M.; Ulrich, S.; Stueber, M.; Seifert, H. J.
2017. 23rd International QUENCH Workshop, Karlsruhe Institute of Technology, Karlsruhe, Germany, 17.-19.10.2017. doi:10.5445/IR/1000076201
High-temperature oxidation behavior of classical zirconium alloys and new ATF cladding materials
Steinbrück, M.; Tang, C.
2017, September 8. The 3rd Asian Nuclear Fuel Conference, September 8-9, 2017, Jeju-do, K
Protective coatings on zirconium-based alloys as accident-Tolerant fuel (ATF) claddings
Tang, C.; Stueber, M.; Seifert, H. J.; Steinbrueck, M.
2017. Corrosion reviews, 35 (3), 141–165. doi:10.1515/corrrev-2017-0010
Synthesis and characterization of Ti2AlC coatings by magnetron sputtering from three elemental targets and ex-situ annealing
Tang, C.; Klimenkov, M.; Jaentsch, U.; Leiste, H.; Rinke, M.; Ulrich, S.; Steinbrück, M.; Seifert, H. J.; Stueber, M.
2017. Surface and coatings technology, 309, 445–455. doi:10.1016/j.surfcoat.2016.11.090
High temperature oxidation behavior of Kanthal APM and D alloys in steam
Tang, C.; Steinbrück, M.; Grosse, M.; Jianu, A.; Weisenburger, A.; Seifert, H. J.
2016. International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016. Proceedings on CD-ROM, 2112–2119, American Nuclear Society (ANS)
Deposition and high-temperature steam oxidation behavior of Ti₂AlC coated zircaloy-4
Tang, C.; Stüber, M.; Steinbrück, M.; Große, M.; Ulrich Sven; Seifert, H. J.
2016. 16th International QUENCH Workshop (2010), Karlsruhe, Deutschland, 16.–18. November 2010
High temperature oxidation behavior of Kanthal APM and D alloys in steam
Tang, C.; Steinbrück, M.; Grosse, M.; Jianu, A.; Weisenburger, A.; Seifert, H. J.
2016. International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016
Preparation of titanium by electrochemical reduction of titanium dioxide powder in molten SrCl2-KCl
Tang, C.; Yu, X.; Chen, J.; Han, Q.; Liu, K.
2016. Journal of alloys and compounds, 684, 699–706. doi:10.1016/j.jallcom.2016.05.206
Assessment of high-temperature steam oxidation behavior of Zircaloy-4 with Ti₂AlC coating deposited by magnetron sputtering
Tang, C.; Stüber, M.; Steinbrück, M.; Grosse, M.; Ulrich, S.; Seifert, H. J.
2016. NuMat2016: The Nuclear Materials Conference, Montpellier, F, November 7-10, 2016
High temperature oxidation behavior of FeCrAl(RE) alloy in steam
Tang, C.; Steinbrück, M.; Grosse, M.; Jianu, A.; Weisenburger, A.; Seifert, H. J.
2016. International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016
High temperature steam oxidation behavior of potential cladding materials FeCrAl alloy and Ti₂AlC MAX phase
Tang, C.; Steinbrück, M.; Große, M.; Jianu, A.; Weisenburger, A.; Seifert, H. J.
2015. 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015
High temperature steam oxidation behavior of potential cladding materials FeCrAl alloy and Ti₂AlC MAX phase
Tang, C.; Steinbrück, M.; Große, M.; Jianu, A.; Weisenburger, A.; Seifert, H. J.
2015. Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)