High-Temperature Materials Chemistry
Management: Dr. Martin Steinbrück
The High Temperature Materials Chemistry group has a worldwide recognized expertise in the field of high temperature oxidation and corrosion of materials for energy technology. Applications range from nuclear safety research to new materials for gas turbines. The working group has various high-temperature facilities that allow materials to be characterized in defined atmospheres up to 2000°C.
Research topics
Neutron radiography image sequence of hydrogen diffusion in a Zry-4 cylinder at 900 °C
- We have a large expertise in the field of oxidation of zirconium alloys in different atmospheres (steam, air, oxygen, nitrogen, mixtures of these) in the temperature range 600-1600 °C as well as the interaction of hydrogen with zirconium.
- Neutron radiography and tomography are used, among other things, to investigate the behaviour of hydrogen in metals in cooperation with various neutron sources. One field of application is the long-term interim storage of spent fuel elements in dry interim storage facilities (CASTOR casks).
- Our laboratory is recognized worldwide for the qualification of new accident tolerant cladding materials up to very high temperatures of 2000°C (ATF=Accident Tolerant Fuel).
Formation of zirconium nitride ZrN (golden phase) during the oxidation of Zircaloy-4 in air (left) and during the reaction of oxidized Zircaloy-4 with nitrogen (right).
Test engineering
- High Temperature Thermobalance Netzsch STA 449 with Steam Furnace and MS Coupling
- Setaram High Performance symmetrical TGA system up to 1700 °C
- Various high temperature furnaces (resistance heating, inductive heating) for reactions in defined atmospheres (air, oxygen, nitrogen, hydrogen, steam etc.) up to 1600 °C and in inert atmospheres up to 2300 °C.
- Analysis of gaseous reaction products by mass spectrometry in the percentage and ppm range (IPI GAM3000).
- INRRO facility for in-situ analysis of hydrogen absorption and diffusion in zirconium alloys by neutron radiography.
- QUENCH-SR single-rod test facility with quenching devices.
- QUENCH facility for bundle experiments for quenching of a superheated reactor core (at and operated together with Nuclear Safety Research Group).
- Metallographic laboratory, light microscopy, SEM-EDX
Cooperations
CSARP (Cooperative Severe Accident Research Program of the US Nuclear Regulatory Commission)
EC Research Program IL TROVATORE (Innovative cladding materials for advanced accident-tolerant energy systems)
IAEA Cooperative Research Program on Testing and Simulation of Advanced Technology Fuels (ATF-TS)
OECD-NEA activities on ATF cladding materials QUENCH-ATF and TOPATF
OECD-NEA project TCOFF (Thermodynamic Characterization of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima-Daiichi Nuclear Power Station)
BMWi Project SPIZWURZ (Stress-induced hydrogen rearrangement in fuel rod cladding tubes during long-term interim storage)
Publications
Modelling the morphology of hydrides in fuel rod cladding under the conditions of the long-term bundle test in the framework of the SPIZWURZ project
Kolesnik, M.; Stuckert, J.; Grosse, M.
2024. Proceedings of TopFuel 2024, Grenoble, 29th September - 3rd October 2024, paper 35
Kolesnik, M.; Stuckert, J.; Grosse, M.
2024. Proceedings of TopFuel 2024, Grenoble, 29th September - 3rd October 2024, paper 35
Investigations of the SPIZWURZ bundle after the 250 day-long dry-storage simulation
Weick, S.; Grosse, M.; Roessger, C.; Stuckert, J.
2024. Proceedings of TopFuel 2024, Article no: 166
Weick, S.; Grosse, M.; Roessger, C.; Stuckert, J.
2024. Proceedings of TopFuel 2024, Article no: 166
Phase formation, structure and properties of quaternary MAX phase thin films in the Cr-V-C-Al system: A combinatorial study
Tang, C.; Dürrschnabel, M.; Jäntsch, U.; Klimenkov, M.; Steinbrück, M.; Ulrich, S.; Hans, M.; Schneider, J. M.; Stüber, M.
2024. Journal of the European Ceramic Society, 44 (15), Art.-Nr.: 116763. doi:10.1016/j.jeurceramsoc.2024.116763
Tang, C.; Dürrschnabel, M.; Jäntsch, U.; Klimenkov, M.; Steinbrück, M.; Ulrich, S.; Hans, M.; Schneider, J. M.; Stüber, M.
2024. Journal of the European Ceramic Society, 44 (15), Art.-Nr.: 116763. doi:10.1016/j.jeurceramsoc.2024.116763
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, 101 (4), 621–647. doi:10.1007/s11085-024-10229-y
Steinbrueck, M.; Grosse, M.; Tang, C.; Stuckert, J.; Seifert, H. J.
2024. High Temperature Corrosion of Materials, 101 (4), 621–647. doi:10.1007/s11085-024-10229-y
Investigating Hydrogen in Zirconium Alloys by Means of Neutron Imaging
Weick, S.; Grosse, M.
2024. Materials, 17 (4), 781. doi:10.3390/ma17040781
Weick, S.; Grosse, M.
2024. Materials, 17 (4), 781. doi:10.3390/ma17040781
Hydrogenation of claddings in the new developed HOKI oven and performance of the long-term bundle test under dry storage conditions in the framework of the SPIZWURZ project
Stuckert, J.; Rössger, C.; Moch, J.; Grosse, M.; Weick, S.
2023, December 5. 28th International QUENCH Workshop (2023), Karlsruhe, Germany, December 5–7, 2023
Stuckert, J.; Rössger, C.; Moch, J.; Grosse, M.; Weick, S.
2023, December 5. 28th International QUENCH Workshop (2023), Karlsruhe, Germany, December 5–7, 2023
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
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
Development of in-situ Delayed Hydride Cracking tests using neutron imaging to study the H redistribution in Zr-2.5%Nb
Soria, S. R.; Gomez, A.; Grosse, M.; Schulz, M.; Santisteban, J. R.; Vizcaino, P.
2023. Journal of Physics: Conference Series, 2605 (1), 012036. doi:10.1088/1742-6596/2605/1/012036
Soria, S. R.; Gomez, A.; Grosse, M.; Schulz, M.; Santisteban, J. R.; Vizcaino, P.
2023. Journal of Physics: Conference Series, 2605 (1), 012036. doi:10.1088/1742-6596/2605/1/012036
Hydrogen diffusion in Zr-2.5Nb pressure tubes specimens between 300°C-400°C by in-situ neutron imaging experiments
Stella, V. M.; Soria, S. R.; Gomez, A.; Grosse, M.; Schulz, M.; Santisteban, J. R.
2023. Journal of Physics: Conference Series, 2605 (1), Art.-Nr.: 012037. doi:10.1088/1742-6596/2605/1/012037
Stella, V. M.; Soria, S. R.; Gomez, A.; Grosse, M.; Schulz, M.; Santisteban, J. R.
2023. Journal of Physics: Conference Series, 2605 (1), Art.-Nr.: 012037. doi:10.1088/1742-6596/2605/1/012037
The SPIZWURZ project – Experimental investigations and modeling of the behavior of hydrogen in zirconium alloys under long-term dry storage conditions
Grosse, M.; Boldt, F.; Herm, M.; Roessger, C.; Stuckert, J.; Weick, S.; Nahm, D.
2024. Nuclear Engineering and Technology, 56, 824–831. doi:10.1016/j.net.2023.09.027
Grosse, M.; Boldt, F.; Herm, M.; Roessger, C.; Stuckert, J.; Weick, S.; Nahm, D.
2024. Nuclear Engineering and Technology, 56, 824–831. doi:10.1016/j.net.2023.09.027
Evaluation of the delayed hydrogen cracking behavior and the hydrogen diffusion coefficient for different microstructures of the Zr-2.5%Nb alloy
Gómez, A. G.; Ponce, J. P.; Grosse, M.; Soria, S.; Condó, A.; Flores, A.; Schulz, M.; Vizcaíno, P.; Santisteban, J. R.
2023. Journal of Nuclear Materials, 587, Art.Nr.:154725. doi:10.1016/j.jnucmat.2023.154725
Gómez, A. G.; Ponce, J. P.; Grosse, M.; Soria, S.; Condó, A.; Flores, A.; Schulz, M.; Vizcaíno, P.; Santisteban, J. R.
2023. Journal of Nuclear Materials, 587, Art.Nr.:154725. doi:10.1016/j.jnucmat.2023.154725
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
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 V
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
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
Experimental and modelling results of the QUENCH-20 experiment with BWR test bundle
Stuckert, J.; Bechta, S.; Hollands, T.; Isaksson, P.; Steinbrueck, M.
2023. Nuclear Engineering and Design, 410, Article no: 112391. doi:10.1016/j.nucengdes.2023.112391
Stuckert, J.; Bechta, S.; Hollands, T.; Isaksson, P.; Steinbrueck, M.
2023. Nuclear Engineering and Design, 410, Article no: 112391. doi:10.1016/j.nucengdes.2023.112391
Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment
Doyle, P.; Stuckert, J.; Grosse, M.; Steinbrück, M.; Nelson, A. T.; Harp, J.; Terrani, K.
2023. Journal of Nuclear Materials, 580, Article no: 154433. doi:10.1016/j.jnucmat.2023.154433
Doyle, P.; Stuckert, J.; Grosse, M.; Steinbrück, M.; Nelson, A. T.; Harp, J.; Terrani, K.
2023. Journal of Nuclear Materials, 580, Article no: 154433. doi:10.1016/j.jnucmat.2023.154433
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
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, October 19. 4th International Conference on Materials: Advanced and Emerging Materials (2022), Barcelona, Spain, October 19–21, 2022
Tang, C.; Dürrschnabel, M.; Jäntsch, U.; Klimenkov, M.; Steinbrück, M.; Ulrich, S.; Hans, M.; Schneider, J. M.; Stüber, M.
2022, October 19. 4th International Conference on Materials: Advanced and Emerging Materials (2022), Barcelona, Spain, October 19–21, 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
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
Effect of steam and oxygen starvation on severe accident progression with air ingress
Farkas, R.; Hózer, Z.; Nagy, I.; Vér, N.; Horváth, M.; Steinbrück, M.; Stuckert, J.; Grosse, M.
2022. Nuclear Engineering and Design, 396, 111884. doi:10.1016/j.nucengdes.2022.111884
Farkas, R.; Hózer, Z.; Nagy, I.; Vér, N.; Horváth, M.; Steinbrück, M.; Stuckert, J.; Grosse, M.
2022. Nuclear Engineering and Design, 396, 111884. doi:10.1016/j.nucengdes.2022.111884
Results of the bundle test QUENCH-19 with FeCrAl claddings
Stuckert, J.; Grosse, M.; Steinbrück, M.
2022. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000148370
Stuckert, J.; Grosse, M.; Steinbrück, M.
2022. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000148370
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
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
Oxidation of Silicon Carbide Composites for Nuclear Applications at Very High Temperatures in Steam
Steinbrueck, M.; Grosse, M.; Stegmaier, U.; Braun, J.; Lorrette, C.
2022. Coatings, 12 (7), Article: 875. doi:10.3390/coatings12070875
Steinbrueck, M.; Grosse, M.; Stegmaier, U.; Braun, J.; Lorrette, C.
2022. Coatings, 12 (7), Article: 875. doi:10.3390/coatings12070875
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
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
Corrosion behavior of Al-containing MAX-phase coatings exposed to oxygen containing molten Pb at 600 °C
Shi, H.; Azmi, R.; Han, L.; Tang, C.; Weisenburger, A.; Heinzel, A.; Maibach, J.; Stüber, M.; Wang, K.; Müller, G.
2022. Corrosion Science, 201, Art.-Nr.: 110275. doi:10.1016/j.corsci.2022.110275
Shi, H.; Azmi, R.; Han, L.; Tang, C.; Weisenburger, A.; Heinzel, A.; Maibach, J.; Stüber, M.; Wang, K.; Müller, G.
2022. Corrosion Science, 201, Art.-Nr.: 110275. doi:10.1016/j.corsci.2022.110275
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
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
The Effect of Annealing Temperature on the Microstructure and Properties of Cr–C–Al Coatings on Zircaloy-4 for Accident-Tolerant Fuel (ATF) Applications
Tang, C.; Steinbrück, M.; Grosse, M.; Ulrich, S.; Stüber, M.
2022. Coatings, 12 (2), Art.-Nr.: 167. doi:10.3390/coatings12020167
Tang, C.; Steinbrück, M.; Grosse, M.; Ulrich, S.; Stüber, M.
2022. Coatings, 12 (2), Art.-Nr.: 167. doi:10.3390/coatings12020167
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
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
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
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
Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview
Pham, H. V.; Kurata, M.; Steinbrueck, M.
2021. Thermo, 1 (2), 151–167. doi:10.3390/thermo1020011
Pham, H. V.; Kurata, M.; Steinbrueck, M.
2021. Thermo, 1 (2), 151–167. doi:10.3390/thermo1020011
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
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
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
In Situ Neutron Radiography Investigations of Hydrogen Related Processes in Zirconium Alloys
Grosse, M.; Schillinger, B.; Kaestner, A.
2021. Applied Sciences, 11 (13), Art.-Nr.: 5775. doi:10.3390/app11135775
Grosse, M.; Schillinger, B.; Kaestner, A.
2021. Applied Sciences, 11 (13), Art.-Nr.: 5775. doi:10.3390/app11135775
High-temperature oxidation and hydrothermal corrosion of textured Cr
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
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
Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release
Stuckert, J.; Steinbrueck, M.; Kalilainen, J.; Lind, T.; Birchley, J.
2021. Nuclear engineering and design, 379, Art.-Nr.: 111267. doi:10.1016/j.nucengdes.2021.111267
Stuckert, J.; Steinbrueck, M.; Kalilainen, J.; Lind, T.; Birchley, J.
2021. Nuclear engineering and design, 379, Art.-Nr.: 111267. doi:10.1016/j.nucengdes.2021.111267
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, Spain, October 24–28, 2021
Tang, C.; Grosse, M.; Steinbrück, M.; Ulrich, S.; Seifert, H. J.; Stüber, M.
2021. TopFuel (2021), Santander, Spain, October 24–28, 2021
High-Temperature Oxidation of Chrome-Nickel Alloy
Chalupová, A.; Steinbrück, M.; Grosse, M.; Krejčí, J.; Ševeček, M.
2020. Acta polytechnica, 28, 8–14. doi:10.14311/APP.2020.28.0008
Chalupová, A.; Steinbrück, M.; Grosse, M.; Krejčí, J.; Ševeček, M.
2020. Acta polytechnica, 28, 8–14. doi:10.14311/APP.2020.28.0008
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
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
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
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
Hydrogen diffusion and precipitation in duplex zirconium nuclear fuel cladding quantified by high-resolution neutron imaging
Gong, W.; Trtik, P.; Colldeweih, A. W.; Duarte, L. I.; Grosse, M.; Lehmann, E.; Bertsch, J.
2019. Journal of nuclear materials, 526, Art.-Nr. 151757. doi:10.1016/j.jnucmat.2019.151757
Gong, W.; Trtik, P.; Colldeweih, A. W.; Duarte, L. I.; Grosse, M.; Lehmann, E.; Bertsch, J.
2019. Journal of nuclear materials, 526, Art.-Nr. 151757. doi:10.1016/j.jnucmat.2019.151757
Investigation of the 3D hydrogen distribution in zirconium alloys by means of neutron tomography – Paper presented at the Symposium “Tomographic and Radiographic Imaging with Synchrotron X-rays and Neutrons” of the MSE 2018, 26–28 September 2018, Darmstadt, Germany
Grosse, M.; Schillinger, B.; Trtik, P.; Kardjilov, N.; Steinbrück, M.
2020. International journal of materials research, 111 (1), 40–46. doi:10.3139/146.111863
Grosse, M.; Schillinger, B.; Trtik, P.; Kardjilov, N.; Steinbrück, M.
2020. International journal of materials research, 111 (1), 40–46. doi:10.3139/146.111863
Results of the QUENCH-LOCA experimental program at KIT
Stuckert, J.; Grosse, M.; Steinbrueck, M.; Walter, M.; Wensauer, A.
2020. Journal of nuclear materials, 534, Article: 152143. doi:10.1016/j.jnucmat.2020.152143
Stuckert, J.; Grosse, M.; Steinbrueck, M.; Walter, M.; Wensauer, A.
2020. Journal of nuclear materials, 534, Article: 152143. doi:10.1016/j.jnucmat.2020.152143
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.; et al.
2020. International Nuclear Fuel Cycle Conference, GLOBAL 2019: Seattle, WA, USA, 22–27 September 2019, 283–290, ANS
Ševeček, M.; Krejčí, J.; Chalupová, A.; Kabátová, J.; Manoch, F.; Kočí, J.; Cvrček, L.; Tang, C.; Steinbrűck, M.; Grosse, M.; et al.
2020. International Nuclear Fuel Cycle Conference, GLOBAL 2019: Seattle, WA, USA, 22–27 September 2019, 283–290, ANS
Oxidation and quench behavior of cold spraying Cr-coated zircaloy fuel cladding under severe accident scenarios
Tang, C.; Grosse, M.; Steinbrueck, M.; Shirvan, K.
2020. International Nuclear Fuel Cycle Conference, GLOBAL 2019: Seattle, WA, USA, 22–27 September 2019, 855–863, ANS
Tang, C.; Grosse, M.; Steinbrueck, M.; Shirvan, K.
2020. International Nuclear Fuel Cycle Conference, GLOBAL 2019: Seattle, WA, USA, 22–27 September 2019, 855–863, 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)
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)
Textured growth of polycrystalline MAX phase carbide coatings via thermal annealing of M/C/Al multilayers
Tang, C.; Steinbrück, M.; Klimenkov, M.; Jäntsch, U.; Seifert, H. J.; Ulrich, S.; Stüber, M.
2020. Journal of vacuum science & technology / A, 38 (1), Article No.013401. doi:10.1116/1.5131544
Tang, C.; Steinbrück, M.; Klimenkov, M.; Jäntsch, U.; Seifert, H. J.; Ulrich, S.; Stüber, M.
2020. Journal of vacuum science & technology / A, 38 (1), Article No.013401. doi:10.1116/1.5131544
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
Tang, C.; Grosse, M.; Martin Steinbrueck; Shirvan, K.
2019. TopFuel 2019, 855–863
Results of the bundle test QUENCH-19 with FeCrAl claddings
Stuckert, J.; Grosse, M.; Steinbrueck, M.; Terrani, K.
2019. Proceedings of Global/Top Fuel 2019, Seattle, WA, September 22-26, 2019, 922–927, American Nuclear Society (ANS)
Stuckert, J.; Grosse, M.; Steinbrueck, M.; Terrani, K.
2019. Proceedings of Global/Top Fuel 2019, Seattle, WA, September 22-26, 2019, 922–927, American Nuclear Society (ANS)
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.; et al.
2019. Top Fuel 2019, American Nuclear Society, Seattle, WA, September, 22-26, 283–290, Greyden Press
Ševeček, M.; Krejčí, J.; Chalupová, A.; Kabátová, J.; Manoch, F.; Kočí, J.; Cvrček, L.; Tang, C.; Steinbrűck, M.; Grosse, M.; et al.
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
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
Oxidation of SiC
Steinbrueck, M.; Angelici Avincola, V.; Markel, I. J.; Stegmaier, U.; Gerhards, U.; Seifert, H. J.
2019. Journal of nuclear materials, 517, 337–348. doi:10.1016/j.jnucmat.2019.02.024
Steinbrueck, M.; Angelici Avincola, V.; Markel, I. J.; Stegmaier, U.; Gerhards, U.; Seifert, H. J.
2019. Journal of nuclear materials, 517, 337–348. doi:10.1016/j.jnucmat.2019.02.024
Synthesis and high-temperature oxidation of ternary carbide coatings on zirconium-based alloy cladding. PhD dissertation
Tang, C.
2019. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000091676
Tang, C.
2019. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000091676
Preliminary interpretative analysis of the QUENCH-18 bundle test using SCDAPSim/mod3.5
Birchley, J. C.; Stuckert, J.; Steinbrueck, M.; Grosse, M.
2019. Annals of nuclear energy, 130, 20–33. doi:10.1016/j.anucene.2019.02.022
Birchley, J. C.; Stuckert, J.; Steinbrueck, M.; Grosse, M.
2019. Annals of nuclear energy, 130, 20–33. doi:10.1016/j.anucene.2019.02.022
Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging = Neutronenradiographie- und -tomographieuntersuchungen der Wasserstoffdiffusion und -verteilung in Zirkonium
Grosse, M.; Santisteban, J. R.; Bertsch, J.; Schillinger, B.; Kaestner, A.; Daymond, M. R.; Kardjilov, N.
2018. Kerntechnik, 83 (6), 495–501. doi:10.3139/124.110946
Grosse, M.; Santisteban, J. R.; Bertsch, J.; Schillinger, B.; Kaestner, A.; Daymond, M. R.; Kardjilov, N.
2018. Kerntechnik, 83 (6), 495–501. doi:10.3139/124.110946
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, Germany, September 26–28, 2018
Tang, C.; Steinbrück, M.; Grosse, M.; Sven Ulrich; Stueber, M.; Seifert, H. J.
2018, September 28. Materials Science and Engineering Congress (MSE 2018), Darmstadt, Germany, September 26–28, 2018
Update of the QUENCH program
Steinbrueck, M.; Stuckert, J.; Grosse, M.
2018. 24th International QUENCH Workshop (2018), Karlsruhe, Germany, November 13–15, 2018
Steinbrueck, M.; Stuckert, J.; Grosse, M.
2018. 24th International QUENCH Workshop (2018), Karlsruhe, Germany, November 13–15, 2018
Improvement of the high-temperature oxidation resistance of Zr alloy cladding by surface modification with aluminium-containing ternary carbide coatings
Tang, C.; Steinbrueck, M.; Grosse, M.; Ulrich, S.; Stueber, M.; Seifert, H. J.
2018. International Congress on Advances in Nuclear Power Plants: Charlotte, North Carolina, USA, 8-11 April 2018, 694–700, Curran
Tang, C.; Steinbrueck, M.; Grosse, M.; Ulrich, S.; Stueber, M.; Seifert, H. J.
2018. International Congress on Advances in Nuclear Power Plants: Charlotte, North Carolina, USA, 8-11 April 2018, 694–700, Curran
Assessing Silicon Carbide Ceramics and Composites for Energy-Related Applications
Mingazzini, C.; Sauder, C.; Braun, J.; Scafe, M.; Rinaldi, A.; Hansen, K. K.; Steinbrueck, M.
2018. 2018 IEEE International Conference on Environment and Electrical Engineering and 2018 IEEE Industrial and Commercial Power Systems Europe (EEEIC / I&CPS Europe), Palermo, Italien, 12.06.2018-15.06.2018, 1–6, Institute of Electrical and Electronics Engineers (IEEE). doi:10.1109/EEEIC.2018.8494444
Mingazzini, C.; Sauder, C.; Braun, J.; Scafe, M.; Rinaldi, A.; Hansen, K. K.; Steinbrueck, M.
2018. 2018 IEEE International Conference on Environment and Electrical Engineering and 2018 IEEE Industrial and Commercial Power Systems Europe (EEEIC / I&CPS Europe), Palermo, Italien, 12.06.2018-15.06.2018, 1–6, Institute of Electrical and Electronics Engineers (IEEE). doi:10.1109/EEEIC.2018.8494444
First Results of the QUENCH-ALISA Bundle Test
Stuckert, J.; Steinbrueck, M.; Kalilainen, J.; Lind, T.; Zhang, Y.
2018. 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Quingdao, China, 14 - 18 October 2018, Paper 918
Stuckert, J.; Steinbrueck, M.; Kalilainen, J.; Lind, T.; Zhang, Y.
2018. 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Quingdao, China, 14 - 18 October 2018, Paper 918
First Results of the QUENCH-ALISA Bundle Test
Stuckert, J.; Steinbrueck, M.; Kalilainen, J.; Lind, T.; Zhang, Y.
2018, October 14. 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 2018), Qingdao, China, October 14–18, 2018
Stuckert, J.; Steinbrueck, M.; Kalilainen, J.; Lind, T.; Zhang, Y.
2018, October 14. 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 2018), Qingdao, China, October 14–18, 2018
On the EU-Japan roadmap for experimental research on corium behavior
Bechta, S.; Ma, W.; Miassoedov, A.; Journeau, C.; Okamoto, K.; Manara, D.; Bottomley, D.; Kurata, M.; Sehgal, B. R.; Steinbrueck, M.; et al.
2019. Annals of nuclear energy, 124, 541–547. doi:10.1016/j.anucene.2018.10.019
Bechta, S.; Ma, W.; Miassoedov, A.; Journeau, C.; Okamoto, K.; Manara, D.; Bottomley, D.; Kurata, M.; Sehgal, B. R.; Steinbrueck, M.; et al.
2019. Annals of nuclear energy, 124, 541–547. doi:10.1016/j.anucene.2018.10.019
Influence of composition and heating schedules on compatibility of FeCrAl alloys with high-temperature steam
Tang, C.; Jianu, A.; Steinbrueck, M.; Grosse, M.; Weisenburger, A.; Seifert, H. J.
2018. Journal of nuclear materials, 511, 496–507. doi:10.1016/j.jnucmat.2018.09.026
Tang, C.; Jianu, A.; Steinbrueck, M.; Grosse, M.; Weisenburger, A.; Seifert, H. J.
2018. Journal of nuclear materials, 511, 496–507. doi:10.1016/j.jnucmat.2018.09.026
Determinación de bajas concentraciones de hidrógeno en aleaciones de circonio utilizando radiografía de neutrones como técnica no destructiva
Buitrago, N. L.; Santisteban, J.; Marín, J.; Tartaglione, A.; Daymond, M.; Grosse, M.
2018. Revista matéria, 23 (2), e-12105. doi:10.1590/S1517-707620180002.0439
Buitrago, N. L.; Santisteban, J.; Marín, J.; Tartaglione, A.; Daymond, M.; Grosse, M.
2018. Revista matéria, 23 (2), e-12105. doi:10.1590/S1517-707620180002.0439
Deposition, characterization and high-temperature steam oxidation behavior of single-phase Ti
Tang, C.; Steinbrueck, M.; Stueber, M.; Grosse, M.; Yu, X.; Ulrich, S.; Seifert, H. J.
2018. Corrosion science, 135, 87–98. doi:10.1016/j.corsci.2018.02.035
Tang, C.; Steinbrueck, M.; Stueber, M.; Grosse, M.; Yu, X.; Ulrich, S.; Seifert, H. J.
2018. Corrosion science, 135, 87–98. doi:10.1016/j.corsci.2018.02.035
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
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
In Situ Investigations of the Hydrogen Uptake of Zirconium Alloys during Steam Oxidation
Grosse, M.; Steinbrueck, M.; Schillinger, B.; Kaestner, A.
2018. Zirconium in the Nuclear Industry: 18th International Symposium, Hilton Head Island, SC, USA, May 15 - 19, 2016. Ed.: R. Comstock, 1114–1135, ASTM International. doi:10.1520/STP159720160041
Grosse, M.; Steinbrueck, M.; Schillinger, B.; Kaestner, A.
2018. Zirconium in the Nuclear Industry: 18th International Symposium, Hilton Head Island, SC, USA, May 15 - 19, 2016. Ed.: R. Comstock, 1114–1135, ASTM International. doi:10.1520/STP159720160041
In-situ neutron radiography investigations of the reaction of Zircaloy-4 in steam, nitrogen/steam and air/steam atmospheres
Grosse, M.; Pulvermacher, S.; Steinbrück, M.; Schillinger, B.
2018. Physica / B, 551, 244–248. doi:10.1016/j.physb.2018.03.030
Grosse, M.; Pulvermacher, S.; Steinbrück, M.; Schillinger, B.
2018. Physica / B, 551, 244–248. doi:10.1016/j.physb.2018.03.030
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
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
Determination of very low concentrations of hydrogen in zirconium alloys by neutron imaging
Buitrago, N. L.; Santisteban, J. R.; Tartaglione, A.; Marín, J.; Barrow, L.; Daymond, M. R.; Schulz, M.; Grosse, M.; Tremsin, A.; Lehmann, E.; et al.
2018. Journal of nuclear materials, 503, 98–109. doi:10.1016/j.jnucmat.2018.02.048
Buitrago, N. L.; Santisteban, J. R.; Tartaglione, A.; Marín, J.; Barrow, L.; Daymond, M. R.; Schulz, M.; Grosse, M.; Tremsin, A.; Lehmann, E.; et al.
2018. Journal of nuclear materials, 503, 98–109. doi:10.1016/j.jnucmat.2018.02.048
Experimental program QUENCH at KIT on core degradation during reflooding under LOCA conditions and in the early phase of a severe accident
Stuckert, J.; Steinbrueck, M.; Grosse, M.
2015. "Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents", Chengdu, China, 28 October–1 November 2013, 281–297, IAEA
Stuckert, J.; Steinbrueck, M.; Grosse, M.
2015. "Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents", Chengdu, China, 28 October–1 November 2013, 281–297, IAEA
Influence of nitrogen on the oxidation behavior of Zircaloy-4-results of in-situ neutron radiography investigations
Grosse, M.; Pulvermacher, S.; Steinbrück, M.; Schillinger, B.
2017. A New Paradigm in Nuclear Power Safety : Proceedings of the International Congress on Advances in Nuclear Power Plants, ICAPP 2017, Fukui and Kyoto, Japan, 24th - 28th April 2017, Atomic Energy Society of Japan
Grosse, M.; Pulvermacher, S.; Steinbrück, M.; Schillinger, B.
2017. A New Paradigm in Nuclear Power Safety : Proceedings of the International Congress on Advances in Nuclear Power Plants, ICAPP 2017, Fukui and Kyoto, Japan, 24th - 28th April 2017, Atomic Energy Society of Japan
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
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 tests of silicon carbide composite cladding under GFR conditions
Angelici Avincola, V.; Fitzgerald, K.; Shepherd, D.; Kinay, D.; Sauder, C.; Steinbrueck, M.
2017. Energy procedia, 127, 320–328. doi:10.1016/j.egypro.2017.08.116
Angelici Avincola, V.; Fitzgerald, K.; Shepherd, D.; Kinay, D.; Sauder, C.; Steinbrueck, M.
2017. Energy procedia, 127, 320–328. doi:10.1016/j.egypro.2017.08.116
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
Steinbrück, M.; Tang, C.
2017, September 8. The 3rd Asian Nuclear Fuel Conference, September 8-9, 2017, Jeju-do, K
Safest roadmap for corium experimental research in Europe
Journeau, C.; Bouyer, V.; Cassiaut-Louis, N.; Fouquart, P.; Piluso, P.; Ducros, G.; Gossé, S.; Guéneau, C.; Quaini, A.; Steinbrueck, M.; et al.
2017. Journal of risk and uncertainty, 4 (3), Art.Nr. 030901. doi:10.1115/1.4037878
Journeau, C.; Bouyer, V.; Cassiaut-Louis, N.; Fouquart, P.; Piluso, P.; Ducros, G.; Gossé, S.; Guéneau, C.; Quaini, A.; Steinbrueck, M.; et al.
2017. Journal of risk and uncertainty, 4 (3), Art.Nr. 030901. doi:10.1115/1.4037878
Which Resolution can be Achieved in Practice in Neutron Imaging Experiments? – A General View and Application on the Zr - ZrH 2 and ZrO 2 - ZrN Systems
Grosse, M.; Kardjilov, N.
2017. Physics procedia, 88, 266–274. doi:10.1016/j.phpro.2017.06.037
Grosse, M.; Kardjilov, N.
2017. Physics procedia, 88, 266–274. doi:10.1016/j.phpro.2017.06.037
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
Tang, C.; Stueber, M.; Seifert, H. J.; Steinbrueck, M.
2017. Corrosion reviews, 35 (3), 141–165. doi:10.1515/corrrev-2017-0010
Oxidation of Zircaloy-4 in steam-nitrogen mixtures at 600–1200 °C
Steinbrück, M.; Silva, F. O. da; Grosse, M.
2017. Journal of nuclear materials, 490, 226–237. doi:10.1016/j.jnucmat.2017.04.034
Steinbrück, M.; Silva, F. O. da; Grosse, M.
2017. Journal of nuclear materials, 490, 226–237. doi:10.1016/j.jnucmat.2017.04.034
Oxidation behavior of Ti 2 AlC in the temperature range of 1400 °C–1600 °C in steam
Tang, C.; Steinbrück, M.; Große, M.; Bergfeldt, T.; Seifert, H. J.
2017. Journal of nuclear materials, 490, 130–142. doi:10.1016/j.jnucmat.2017.03.016
Tang, C.; Steinbrück, M.; Große, M.; Bergfeldt, T.; Seifert, H. J.
2017. Journal of nuclear materials, 490, 130–142. doi:10.1016/j.jnucmat.2017.03.016
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
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
Experiments on silver-indium-cadmium control rod failure during severe nuclear accidents
Steinbrück, M.; Stegmaier, U.; Grosse, M.
2017. Annals of nuclear energy, 101, 347–358. doi:10.1016/j.anucene.2016.11.039
Steinbrück, M.; Stegmaier, U.; Grosse, M.
2017. Annals of nuclear energy, 101, 347–358. doi:10.1016/j.anucene.2016.11.039
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)
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, Germany, November 16–18, 2010
Tang, C.; Stüber, M.; Steinbrück, M.; Große, M.; Ulrich Sven; Seifert, H. J.
2016. 16th International QUENCH Workshop (2010), Karlsruhe, Germany, November 16–18, 2010
Update of the QUENCH Program
Steinbrück, M.; Stuckert, J.; Grosse, M.
2016. 22nd International QUENCH Workshop, 18-22 October 2016, Karlsruhe Institute of Technology, Karlsruhe, Germany
Steinbrück, M.; Stuckert, J.; Grosse, M.
2016. 22nd International QUENCH Workshop, 18-22 October 2016, Karlsruhe Institute of Technology, Karlsruhe, Germany
The QUENCH Program at KIT
Steinbrück, M.; Stuckert, J.; Grosse, M.
2016. KNF Seminar, KEPCO Nuclear Fuel, 01. November 2016, Daejoen, Korea
Steinbrück, M.; Stuckert, J.; Grosse, M.
2016. KNF Seminar, KEPCO Nuclear Fuel, 01. November 2016, Daejoen, Korea
Oxidation of Zircaloy-4 in steam-nitrogen mixtures at 600-1200°C
Steinbrueck, M.; Grosse, M.; Oliveira da Silva, F.
2016. Proceedings of the 2016 International Congress on Advances in Nuclear Power Plants, ICAPP2016, American Nuclear Society, 535–545, American Nuclear Society (ANS)
Steinbrueck, M.; Grosse, M.; Oliveira da Silva, F.
2016. Proceedings of the 2016 International Congress on Advances in Nuclear Power Plants, ICAPP2016, American Nuclear Society, 535–545, American Nuclear Society (ANS)
Oxidation and hydrogen uptake during high-temperature reaction of zirconium alloys in steam-nitrogen mixtures
Steinbrück, M.; Grosse, M.
2016. 18th International Symposium on Zirconium in Nuclear Industry, 15-19 May 2016, Hilton Head Island, SC, USA
Steinbrück, M.; Grosse, M.
2016. 18th International Symposium on Zirconium in Nuclear Industry, 15-19 May 2016, Hilton Head Island, SC, USA
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
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 oxidation behavior of kanthal APM and d alloys in steam
Tang, C.; Steinbrueck, M.; Grosse, M.; Jianu, A.; Weisenburger, A.; Seifert, H. J.
2016. International Congress on Advances in Nuclear Power Plants, ICAPP 2016; San Francisco; United States; 17 April 2016 through 20 April 2016. Vol. 3, 2112–2119, American Nuclear Society (ANS)
Tang, C.; Steinbrueck, M.; Grosse, M.; Jianu, A.; Weisenburger, A.; Seifert, H. J.
2016. International Congress on Advances in Nuclear Power Plants, ICAPP 2016; San Francisco; United States; 17 April 2016 through 20 April 2016. Vol. 3, 2112–2119, American Nuclear Society (ANS)
Which Resolution can be achieved in Praxis in Neutron Imaging Experiments? - A General View
Grosse, M.; Kardjilov, N.
2016. 8th International Technical Meeting on Neutron Radiography, Beijing, China, September 5-8,2016
Grosse, M.; Kardjilov, N.
2016. 8th International Technical Meeting on Neutron Radiography, Beijing, China, September 5-8,2016
Accident fuel-cladding concepts for light water reactors
Grosse, M.
2016. International Youth Nuclear Congress, Hangzhou, China, July 28, 2016
Grosse, M.
2016. International Youth Nuclear Congress, Hangzhou, China, July 28, 2016
Accident fuel-cladding concepts for light water reactors
Grosse, M.
2016. Workshop on SFP and Fuel Cladding Safety, Pohang, Korea, July 22, 2016
Grosse, M.
2016. Workshop on SFP and Fuel Cladding Safety, Pohang, Korea, July 22, 2016
Experimental investigations and modelling of the reaction of zirconium alloys in nitrogen/oxygen or nitrogen/steam atmospheres
Grosse, M.; Steinbrueck, M.; Maeng, J.; Sung, J.
2016. Workshop on SFP and Fuel Cladding Safety, Pohang, Korea, July 22, 2016
Grosse, M.; Steinbrueck, M.; Maeng, J.; Sung, J.
2016. Workshop on SFP and Fuel Cladding Safety, Pohang, Korea, July 22, 2016
Neutron imaging investigation of hydrogen absorption and diffusion at HT
Grosse, M.
2016. Workshop on SFP and Fuel Cladding Safety, Pohang, Korea, July 22, 2016
Grosse, M.
2016. Workshop on SFP and Fuel Cladding Safety, Pohang, Korea, July 22, 2016
The QUENCH program at KIT
Grosse, M.
2016. Workshop on SFP and Fuel Cladding Safety, Pohang, Korea, July 22, 2016
Grosse, M.
2016. Workshop on SFP and Fuel Cladding Safety, Pohang, Korea, July 22, 2016
In-situ Investigations of the Hydrogen Uptake of Zirconium Alloys during Steam Oxidation
Grosse, M.; Steinbrueck, M.; Schillinger, B.; Kaestner, A.
2016. 18th International Symposium on Zirconium in the Nuclear Industry, Hilton Head Island, SC, May 15-19, 2016
Grosse, M.; Steinbrueck, M.; Schillinger, B.; Kaestner, A.
2016. 18th International Symposium on Zirconium in the Nuclear Industry, Hilton Head Island, SC, May 15-19, 2016
Influence of the steam and oxygen flow rate on the reaction of zirconium in steam/nitrogen and oxygen/nitrogen atmospheres
Grosse, M.; Steinbrück, M.; Maeng, Y.; Sung, J.
2016. International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016. Proceedings on CD-ROM, Paper 16259, American Nuclear Society (ANS)
Grosse, M.; Steinbrück, M.; Maeng, Y.; Sung, J.
2016. International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016. Proceedings on CD-ROM, Paper 16259, American Nuclear Society (ANS)
KIT multi-physics tools for the analysis of design and beyond design basis accidents of light water reactors
Sanchez, V.; Miassoedov, A.; Steinbrueck, M.; Tromm, W.
2016. Kerntechnik, 81 (2), 145–148. doi:10.3139/124.110687
Sanchez, V.; Miassoedov, A.; Steinbrueck, M.; Tromm, W.
2016. Kerntechnik, 81 (2), 145–148. doi:10.3139/124.110687
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
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
Which resolution can be achieved in praxis in neutron imaging expriments? - A general view
Grosse, M.; Kardjilov, N.
2016. International Technical Meeting on Neutron Radiography, September, 4 2016
Grosse, M.; Kardjilov, N.
2016. International Technical Meeting on Neutron Radiography, September, 4 2016
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
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
Influence of the steam and oxygen flow rate on the reaction of zirconium in steam/nitrogen and oxygen/nitrogen atmospheres
Grosse, M.; Steinbrück, M.
2016. International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016
Grosse, M.; Steinbrück, M.
2016. International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 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
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
Oxidation of zircaloy-4 in steam-nitrogen mixtures at 600-1200⁰C
Steinbrück, M.; Grosse, M.; Oliveira da Silva, F.
2016. International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016
Steinbrück, M.; Grosse, M.; Oliveira da Silva, F.
2016. International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016
Proposal of a simple model describing the kinetics of the reaction of zirconium with air and steam/nitrogen gas mixture derived from an atomistic description of the process
Grosse, M.
2015. 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015
Grosse, M.
2015. 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015
Results of neutron imaging investigations of QUENCH-LOCA claddings
Grosse, M.; Roessger, C.; Muttini, E.
2015. 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015
Grosse, M.; Roessger, C.; Muttini, E.
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. 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015
Tang, C.; Steinbrück, M.; Große, M.; Jianu, A.; Weisenburger, A.; Seifert, H. J.
2015. 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015
Proposal of a simple model describing the kinetics of the reaction of zirconium with air and steam/nitrogen gas mixture derived from an atomistic description of the process
Grosse, M.
2015. Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)
Grosse, M.
2015. Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)
Results of neutron imaging investigations of QUENCH-LOCA claddings
Grosse, M.; Roessger, C.; Muttini, E.
2015. Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015. M. Steinbrück, Karlsruher Institut für Technologie (KIT)
Grosse, M.; Roessger, C.; Muttini, E.
2015. Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015. M. Steinbrück, Karlsruher Institut für Technologie (KIT)
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)
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)
Flexible sample environment for high resolution neutron imaging at high temperatures in controlled atmosphere
Makowaka, M. G.; Kuhn, L. T.; Cleemann, L. N.; Lauridsen, E. M.; Bilheux, H. Z.; Molaison, J. J.; Santodonato, L. J.; Tremsin, A. S.; Grosse, M.; Morgano, M.; et al.
2015. Review of scientific instruments, 86 (12), Art. Nr. 125109. doi:10.1063/1.4937615
Makowaka, M. G.; Kuhn, L. T.; Cleemann, L. N.; Lauridsen, E. M.; Bilheux, H. Z.; Molaison, J. J.; Santodonato, L. J.; Tremsin, A. S.; Grosse, M.; Morgano, M.; et al.
2015. Review of scientific instruments, 86 (12), Art. Nr. 125109. doi:10.1063/1.4937615
Oxidation at high temperatures in steam atmosphere and quench of silicon carbide composites for nuclear application
Avincola, V. A.; Grosse, M.; Stegmaier, U.; Steinbrück, M.; Seifert, H. J.
2015. Nuclear engineering and design, 395, 468–478. doi:10.1016/j.nucengdes.2015.10.002
Avincola, V. A.; Grosse, M.; Stegmaier, U.; Steinbrück, M.; Seifert, H. J.
2015. Nuclear engineering and design, 395, 468–478. doi:10.1016/j.nucengdes.2015.10.002
Neutron imaging investigations of the secondary hydriding of nuclear fuel cladding alloys during loss of coolant accidents
Grosse, M.; Roessger, C.; Stuckert, J.; Steinbrueck, M.; Kaestner, A.; Kardjilov, N.; Schillinger, B.
2015. Physics procedia, 69, 436–444. doi:10.1016/j.phpro.2015.07.061
Grosse, M.; Roessger, C.; Stuckert, J.; Steinbrueck, M.; Kaestner, A.; Kardjilov, N.; Schillinger, B.
2015. Physics procedia, 69, 436–444. doi:10.1016/j.phpro.2015.07.061
Secondary hydrogenation of zircaloy-4 cladding tubes during LOCA bundle tests performed at KIT
Roessger, C.; Stuckert, J.; Grosse, M.; Steinbrück, M.
2015. International Conference on Hydrogen Storage Embrittlement and Applications (Hy-SEA 2014), Rio de Janeiro, BR, October 26-30, 2014
Roessger, C.; Stuckert, J.; Grosse, M.; Steinbrück, M.
2015. International Conference on Hydrogen Storage Embrittlement and Applications (Hy-SEA 2014), Rio de Janeiro, BR, October 26-30, 2014
A comparison of core degradation phenomena in the CORA, QUENCH, Phebus SFD and Phebus FP experiments
Haste, T.; Steinbrück, M.; Barrachin, M.; Luze, O. de; Grosse, M.; Stuckert, J.
2015. Nuclear engineering and design, 283, 8–20. doi:10.1016/j.nucengdes.2014.06.035
Haste, T.; Steinbrück, M.; Barrachin, M.; Luze, O. de; Grosse, M.; Stuckert, J.
2015. Nuclear engineering and design, 283, 8–20. doi:10.1016/j.nucengdes.2014.06.035
Quantitative analysis of hydrogen uptake, diffusion and distribution in nuclear fuel rod claddings made of zirconium alloys
Grosse, M.
2015. Neutron news, 26 (2), 31–33. doi:10.1080/10448632.2015.1028277
Grosse, M.
2015. Neutron news, 26 (2), 31–33. doi:10.1080/10448632.2015.1028277
Hydrogen uptake of Zry-4 during reaction in N₂/H₂O atmosphere in the temperature range of 600 - 1100⁰C
Grosse, M.; Steinbrück, M.; Ott, L.; Kaestner, A.
2015. International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, F, May 3-6, 2015
Grosse, M.; Steinbrück, M.; Ott, L.; Kaestner, A.
2015. International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, F, May 3-6, 2015
Hydrogen uptake of Zry-4 during reaction in N₂/H₂O atmosphere in the temperature range of 600 - 1100⁰C
Grosse, M.; Steinbrück, M.; Ott, L.; Kaestner, A.
2015. International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, F, May 3-6, 2015 Proceedings, Paper 15045, Omnipress
Grosse, M.; Steinbrück, M.; Ott, L.; Kaestner, A.
2015. International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, F, May 3-6, 2015 Proceedings, Paper 15045, Omnipress
Corrosion and hydrogen uptake in zirconium claddings irradiated in light water reactors
Abolhassani, S.; Bart, G.; Bertsch, J.; Grosse, M.; Hallstadius, L.; Hermann, A.; Kuri, G.; Ledergerber, G.; Lemaignan, C.; Martin, M.; et al.
2015. Zirconium in the Nuclear Industry : 17th International Symposium, Hyderabad, IND, February 3-7, 2013 West. Ed.: R. J. Comstock, 540–573, ASTM International. doi:10.1520/STP154320130007
Abolhassani, S.; Bart, G.; Bertsch, J.; Grosse, M.; Hallstadius, L.; Hermann, A.; Kuri, G.; Ledergerber, G.; Lemaignan, C.; Martin, M.; et al.
2015. Zirconium in the Nuclear Industry : 17th International Symposium, Hyderabad, IND, February 3-7, 2013 West. Ed.: R. J. Comstock, 540–573, ASTM International. doi:10.1520/STP154320130007
Silicon carbide as accident tolerant cladding: Oxidation and quench at very high temperature
Avincola, V.; Steinbrück, M.; Grosse, M.; Seifert, H. J.
2014. American Nuclear Society (ANS) Student Conference, University Park, PA, April 3-6, 2014
Avincola, V.; Steinbrück, M.; Grosse, M.; Seifert, H. J.
2014. American Nuclear Society (ANS) Student Conference, University Park, PA, April 3-6, 2014
Modeling of the hydrogen distribution in cladding tubes after LOCA
Grosse, M.
2013. 19th International QUENCH Workshop, Karlsruhe, November 19-21, 2013
Grosse, M.
2013. 19th International QUENCH Workshop, Karlsruhe, November 19-21, 2013
Neutron and X-ray imaging investigations concerning the QUENCH program
Grosse, M.; Nshimirimana, R.; Steinbrück, M.; Rössger, C.; Grünzweig, C.; Kaestner, A.; Kardjilov, N.; Onel, Y.
2013. 19th International QUENCH Workshop, Karlsruhe, November 19-21, 2013
Grosse, M.; Nshimirimana, R.; Steinbrück, M.; Rössger, C.; Grünzweig, C.; Kaestner, A.; Kardjilov, N.; Onel, Y.
2013. 19th International QUENCH Workshop, Karlsruhe, November 19-21, 2013
Modeling of the hydrogen distribution in cladding tubes after LOCA
Grosse, M.
2013. Proceedings of the 19th International QUENCH Workshop, Karlsruhe, November 19- 21, 2013. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)
Grosse, M.
2013. Proceedings of the 19th International QUENCH Workshop, Karlsruhe, November 19- 21, 2013. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)
Neutron and X-ray imaging investigations concerning the QUENCH program
Grosse, M.; Nshimirimana, R.; Steinbrück, M.; Rössger, C.; Grünzweig, C.; Kaestner, A.; Kardjilov, N.; Onel, Y.
2013. Proceedings of the 19th International QUENCH Workshop, Karlsruhe, November 19- 21, 2013. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)
Grosse, M.; Nshimirimana, R.; Steinbrück, M.; Rössger, C.; Grünzweig, C.; Kaestner, A.; Kardjilov, N.; Onel, Y.
2013. Proceedings of the 19th International QUENCH Workshop, Karlsruhe, November 19- 21, 2013. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)
Parameters influencing the hydrogen concentration and distribution in cladding tubes after LOCA: Results of bundle-scale experiments and modeling
Grosse, M.; Stuckert, J.; Steinbrück, M.
2014. International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Charlotte, N.C., April 6-9, 2014. Vol. 2, 850–856, American Nuclear Society
Grosse, M.; Stuckert, J.; Steinbrück, M.
2014. International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Charlotte, N.C., April 6-9, 2014. Vol. 2, 850–856, American Nuclear Society
Development, characterization and testing of materials of relevance to nuclear energy sector using neutron beams - A progess report of the IAEA coordinated research project
Grosse, M.; Balagurov, A.; Inozemtsev, V.; Lehmann, E.; Mikula, P.; Ridikas, D.; Törok, G.
2014. International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Charlotte, N.C., April 6-9, 2014. Vol. 3, 2086–2093, American Nuclear Society
Grosse, M.; Balagurov, A.; Inozemtsev, V.; Lehmann, E.; Mikula, P.; Ridikas, D.; Törok, G.
2014. International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Charlotte, N.C., April 6-9, 2014. Vol. 3, 2086–2093, American Nuclear Society
Development, characterization and testing of materials of relevance to nuclear energy sector using neutron beams - A progess report of the IAEA coordinated research project
Grosse, M.; Balagurov, A.; Inozemtsev, V.; Lehmann, E.; Mikula, P.; Ridikas, D.; Törok, G.
2014. International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Charlotte, N.C., April 6-9, 2014
Grosse, M.; Balagurov, A.; Inozemtsev, V.; Lehmann, E.; Mikula, P.; Ridikas, D.; Törok, G.
2014. International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Charlotte, N.C., April 6-9, 2014
Parameters influencing the hydrogen concentration and distribution in cladding tubes after LOCA: Results of bundle-scale experiments and modeling
Grosse, M.; Stuckert, J.; Steinbrück, M.
2014. International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Charlotte, N.C., April 6-9, 2014
Grosse, M.; Stuckert, J.; Steinbrück, M.
2014. International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Charlotte, N.C., April 6-9, 2014
A comparison of core degradation phenomena in the CORA, QUENCH, Phebus SFD and Phebus FP experiments
Haste, T.; Steinbrück, M.; Barrachin, M.; Luze, O. de; Grosse, M.; Stuckert, J.
2013. Proceedings of the 22nd International Conference Nuclear Energy for New Europe (NENE2013), Bled, SLO, September 9-12, 2013. Ed.: L. Cizelj, Nuclear Society of Slovenia
Haste, T.; Steinbrück, M.; Barrachin, M.; Luze, O. de; Grosse, M.; Stuckert, J.
2013. Proceedings of the 22nd International Conference Nuclear Energy for New Europe (NENE2013), Bled, SLO, September 9-12, 2013. Ed.: L. Cizelj, Nuclear Society of Slovenia
Experimental program QUENCH at KIT on core degradation during reflooding under LOCA conditions and in the early phase of a severe accident
Stuckert, J.; Steinbrück, M.; Grosse, M.
2013. Technical Meeting on Modelling of Water-Cooled Fuel Including Design-Basis and Severe Accidents, Chengdu, China, October 28 - November 1, 2013
Stuckert, J.; Steinbrück, M.; Grosse, M.
2013. Technical Meeting on Modelling of Water-Cooled Fuel Including Design-Basis and Severe Accidents, Chengdu, China, October 28 - November 1, 2013
A comparison of core degradation phenomena in the CORA, QUENCH, Phebus SFD and Phebus FP experiments
Haste, T.; Steinbrück, M.; Barrachin, M.; Luze, O. de; Grosse, M.; Stuckert, J.
2013. 22nd International Conference Nuclear Energy for New Europe (NENE2013), Bled, SLO, September 9-12, 2013
Haste, T.; Steinbrück, M.; Barrachin, M.; Luze, O. de; Grosse, M.; Stuckert, J.
2013. 22nd International Conference Nuclear Energy for New Europe (NENE2013), Bled, SLO, September 9-12, 2013
Neutron imaging investigations of the hydrogen related degradation of the mechanical properties of zircaloy-4 cladding tubes
Grosse, M.; Valance, S.; Stuckert, J.; Steinbrück, M.; Walter, M.; Kaestner, A.; Hartmann, S.; Santisteban, J.
2012. MRS Fall Meeting & Exhibit, Boston, Mass., November 25-30, 2012
Grosse, M.; Valance, S.; Stuckert, J.; Steinbrück, M.; Walter, M.; Kaestner, A.; Hartmann, S.; Santisteban, J.
2012. MRS Fall Meeting & Exhibit, Boston, Mass., November 25-30, 2012
Neutron imaging investigations of the hydrogen related degradation of the mechanical properties of zircaloy-4 cladding tubes
Grosse, M.; Valance, S.; Stuckert, J.; Steinbrück, M.; Walter, M.; Kaestner, A.; Hartmann, S.; Santisteban, J.
2013. Advanced Materials Exploration with Neutrons and Synchrotron X-Rays : Proceedings of Symposium VV of MRS Fall Meeting 2012, Boston, MA., November 25-30, 2012, 89–94, MRS. doi:10.1557/opl.2013.364
Grosse, M.; Valance, S.; Stuckert, J.; Steinbrück, M.; Walter, M.; Kaestner, A.; Hartmann, S.; Santisteban, J.
2013. Advanced Materials Exploration with Neutrons and Synchrotron X-Rays : Proceedings of Symposium VV of MRS Fall Meeting 2012, Boston, MA., November 25-30, 2012, 89–94, MRS. doi:10.1557/opl.2013.364
Neutron radiograhy and tomography investigations of the secondary hydriding of zircaloy-4 during simulated loss of coolant nuclear accidents
Grosse, M. K.; Stuckert, J.; Steinbrück, M.; Kaestner, A. P.; Hartmann, S.
2013. Physics Procedia, 43, 294–306. doi:10.1016/j.phpro.2013.03.035
Grosse, M. K.; Stuckert, J.; Steinbrück, M.; Kaestner, A. P.; Hartmann, S.
2013. Physics Procedia, 43, 294–306. doi:10.1016/j.phpro.2013.03.035
Measurement and modeling of the hydrogen distribution in nuclear fuel claddings after loss of coolant accidents
Grosse, M.; Stuckert, J.; Steinbrück, M.; Kaestner, A.
2013. International Conference on Neutron Scattering (ICNS 2013), Edinburgh, GB, July 8-12, 2013
Grosse, M.; Stuckert, J.; Steinbrück, M.; Kaestner, A.
2013. International Conference on Neutron Scattering (ICNS 2013), Edinburgh, GB, July 8-12, 2013
Investigation of the annealing behaviour of hydride precipitates in zircaloy-4
Prestel, S.; Grosse, M.
2012. 18th Internat.QUENCH-Workshop, Karlsruhe, November 20-22, 2012
Prestel, S.; Grosse, M.
2012. 18th Internat.QUENCH-Workshop, Karlsruhe, November 20-22, 2012
Neutron imaging investigations of the hydrogen related degradation of the mechanical properties of zircaloy-4 cladding tubes
Grosse, M.; Valance, S.; Rössger, C.; Kaestner, A.; Hartmann, S.; Santisteban, J.
2012. 18th Internat.QUENCH-Workshop, Karlsruhe, November 20-22, 2012
Grosse, M.; Valance, S.; Rössger, C.; Kaestner, A.; Hartmann, S.; Santisteban, J.
2012. 18th Internat.QUENCH-Workshop, Karlsruhe, November 20-22, 2012
Analysis of the hydrogen distributions in QUENCH-LOCA cladding tubes
Grosse, M.; Stuckert, J.; Steinbrück, M.; Walter, M.; Kaestner, A.
2012. 18th Internat.QUENCH-Workshop, Karlsruhe, November 20-22, 2012
Grosse, M.; Stuckert, J.; Steinbrück, M.; Walter, M.; Kaestner, A.
2012. 18th Internat.QUENCH-Workshop, Karlsruhe, November 20-22, 2012
Investigation of the annealing behaviour of hydride precipitates in zircaloy-4
Prestel, S.; Grosse, M.
2012. Proc.of the 18th Internat.QUENCH Workshop, Karlsruhe, November 20-22, 2012. Hrsg.: M. Steinbrück, CD-ROM, Karlsruher Institut für Technologie (KIT)
Prestel, S.; Grosse, M.
2012. Proc.of the 18th Internat.QUENCH Workshop, Karlsruhe, November 20-22, 2012. Hrsg.: M. Steinbrück, CD-ROM, Karlsruher Institut für Technologie (KIT)
Neutron imaging investigations of the hydrogen related degradation of the mechanical properties of zircaloy-4 cladding tubes
Grosse, M.; Valance, S.; Rössger, C.; Kaestner, A.; Hartmann, S.; Santisteban, J.
2012. Proc.of the 18th Internat.QUENCH Workshop, Karlsruhe, November 20-22, 2012 , 2012. Hrsg.: M. Steinbrück, CD-ROM, Karlsruher Institut für Technologie (KIT)
Grosse, M.; Valance, S.; Rössger, C.; Kaestner, A.; Hartmann, S.; Santisteban, J.
2012. Proc.of the 18th Internat.QUENCH Workshop, Karlsruhe, November 20-22, 2012 , 2012. Hrsg.: M. Steinbrück, CD-ROM, Karlsruher Institut für Technologie (KIT)
Analysis of the hydrogen distributions in QUENCH-LOCA cladding tubes
Grosse, M.; Stuckert, J.; Steinbrück, M.; Walter, M.; Kaestner, A.
2012. Proc.of the 18th Internat.QUENCH Workshop, Karlsruhe, November 20-22, 2012. Hrsg.: M. Steinbrück, CD-ROM, Karlsruher Institut für Technologie (KIT)
Grosse, M.; Stuckert, J.; Steinbrück, M.; Walter, M.; Kaestner, A.
2012. Proc.of the 18th Internat.QUENCH Workshop, Karlsruhe, November 20-22, 2012. Hrsg.: M. Steinbrück, CD-ROM, Karlsruher Institut für Technologie (KIT)
Analysis of the absorbed hydrogen in cladding tubes applied in the QUENCH-LOCA tests
Grosse, M.; Rössger, K.; Stuckert, J.; Steinbrück, M.; Walter, M.; Klimenkov, M.; Kaestner, A.
2012. Internat.Congress on the Advances in Nuclear Power Plants (ICAPP 12), Chicago, Ill., June 24-28, 2012
Grosse, M.; Rössger, K.; Stuckert, J.; Steinbrück, M.; Walter, M.; Klimenkov, M.; Kaestner, A.
2012. Internat.Congress on the Advances in Nuclear Power Plants (ICAPP 12), Chicago, Ill., June 24-28, 2012
Which process occurring in the fuel cladding during nuclear accidents? Contributions of neutron imaging to nuclear safety
Grosse, M.
2012. Vortr.: Queens University, Kingston, CDN, 22.Juni 2012
Grosse, M.
2012. Vortr.: Queens University, Kingston, CDN, 22.Juni 2012
Neutron radiography and tomography investigations of the secondary hydriding of Zry-4 during loss of cooland nuclear accidents
Grosse, M. K.; Stuckert, J.; Steinbrück, M.; Kaestner, A. P.; Hartmann, S.
2012. 7th Internat.Topical Meeting on Neutron Radiography (ITMNR-7), Kingston, CDN, June 16-24
Grosse, M. K.; Stuckert, J.; Steinbrück, M.; Kaestner, A. P.; Hartmann, S.
2012. 7th Internat.Topical Meeting on Neutron Radiography (ITMNR-7), Kingston, CDN, June 16-24
High-temperature oxidation in nuclear reactor systems
Grosse, M.
2012. Feron, D. [Hrsg.] Nuclear Corrosion Science and Engineering Oxford [u.a.] : Woodhead Publ., 2012 (Woodhead Publishing Series in Energy ; 22)
Grosse, M.
2012. Feron, D. [Hrsg.] Nuclear Corrosion Science and Engineering Oxford [u.a.] : Woodhead Publ., 2012 (Woodhead Publishing Series in Energy ; 22)
In-situ investigation of hydrogen diffusion in zircaloy-4 by means of neutron radiography
Grosse, M.; den Berg, M. van; Goulet, C.; Kaestner, A.
2012. Journal of Physics: Conference Series, 340, 0012106/1–8. doi:10.1088/1742-6596/340/1/012106
Grosse, M.; den Berg, M. van; Goulet, C.; Kaestner, A.
2012. Journal of Physics: Conference Series, 340, 0012106/1–8. doi:10.1088/1742-6596/340/1/012106
Secondary hydriding during LOCA - results from the QUENCH-L0 test
Grosse, M.; Stuckert, J.; Steinbrück, M.; Kaestner, A.
2012. Journal of Nuclear Materials, 420, 575–582. doi:10.1016/j.jnucmat.2011.11.045
Grosse, M.; Stuckert, J.; Steinbrück, M.; Kaestner, A.
2012. Journal of Nuclear Materials, 420, 575–582. doi:10.1016/j.jnucmat.2011.11.045
Neutron radiography: a powerful tool for fast, quantitative and non-destructive determination of hydrogen concentration and distribution in zirconium alloys
Grosse, M.
2011. Journal of ASTM International, 8 (4), 575–591. doi:10.1520/JAI103251
Grosse, M.
2011. Journal of ASTM International, 8 (4), 575–591. doi:10.1520/JAI103251
Hydrogen diffusion under stress concentration applied to DHC: a feasibility study using neutron
Valance, S.; Grosse, M.; Bertsch, J.; Kaestner, A.
2011. 17th Internat.QUENCH Workshop, Karlsruhe, November 22-24, 2011
Valance, S.; Grosse, M.; Bertsch, J.; Kaestner, A.
2011. 17th Internat.QUENCH Workshop, Karlsruhe, November 22-24, 2011
Neutron radiography investigations to study the material behaviour in loss of coolant nuclear accidents
Grosse, M.; Kaestner, A.
2011. 2nd Joint Users’ Meeting @ PSI, Villigen, CH, September 15-16, 2011
Grosse, M.; Kaestner, A.
2011. 2nd Joint Users’ Meeting @ PSI, Villigen, CH, September 15-16, 2011
Neutron radiography investigations of the hydrogen uptake of fuel cladding tubes during LOCA and severe accidents
Grosse, M.
2011. IAEA CRP Meeting, Beijing, China, September 19-23, 2011
Grosse, M.
2011. IAEA CRP Meeting, Beijing, China, September 19-23, 2011
Hydrogen diffusion under stress concentration applied to DHC: a feasibility study using neutron
Valance, S.; Grosse, M.; Bertsch, J.; Kaestner, A.
2011. Steinbrück, M. [Hrsg.] Proc.of the 17th Internat.QUENCH Workshop, Karlsruhe, November 22-24, 2011 CD-ROM Karlsruhe : Karlsruhe Inst.of Technology, Campus North, 2011 urn:nbn:de:0005-900129
Valance, S.; Grosse, M.; Bertsch, J.; Kaestner, A.
2011. Steinbrück, M. [Hrsg.] Proc.of the 17th Internat.QUENCH Workshop, Karlsruhe, November 22-24, 2011 CD-ROM Karlsruhe : Karlsruhe Inst.of Technology, Campus North, 2011 urn:nbn:de:0005-900129
Experimental parameters influencing the amount of hydrogen absorbed in Zr alloys during steam oxidation
Grosse, M.
2011. 17th Internat.QUENCH-Workshop, Karlsruhe, November 22-24, 2011
Grosse, M.
2011. 17th Internat.QUENCH-Workshop, Karlsruhe, November 22-24, 2011
Experimental parameters influencing the amount of hydrogen absorbed in Zr alloys during steam oxidation
Grosse, M.
2011. Steinbrück, M. [Hrsg.] Proc.of the 17th Internat.QUENCH Workshop, Karlsruhe, November 22-24, 2011 CD-ROM Karlsruhe : Karlsruhe Inst.of Technology, Campus North, 2011 urn:nbn:de:0005-900129
Grosse, M.
2011. Steinbrück, M. [Hrsg.] Proc.of the 17th Internat.QUENCH Workshop, Karlsruhe, November 22-24, 2011 CD-ROM Karlsruhe : Karlsruhe Inst.of Technology, Campus North, 2011 urn:nbn:de:0005-900129
In-situ investigation of hydrogen diffusion in zircaloy-4 by means of neutron radiography
Grosse, M.; den Berg, M. van; Kaestner, A.; Schillinger, B.
2011. 5th European Conf.on Neutron Scattering (ECNS 2011), Praha, CZ, July 17-22, 2011
Grosse, M.; den Berg, M. van; Kaestner, A.; Schillinger, B.
2011. 5th European Conf.on Neutron Scattering (ECNS 2011), Praha, CZ, July 17-22, 2011
Nitriding behavior of nickel-based superalloys at 1273 K and above
Grosse, M.; Sporn, M.; Menden, M.
2011. Internat.Congress on Advances in Nuclear Power Plants (ICAPP 2011), Nice, F, May 2-5, 2011
Grosse, M.; Sporn, M.; Menden, M.
2011. Internat.Congress on Advances in Nuclear Power Plants (ICAPP 2011), Nice, F, May 2-5, 2011
Secondary hydriding during LOCA - results from the QUENCH-L0 test
Grosse, M.; Stuckert, J.; Steinbrück, M.; Kaestner, A.
2011. European Materials Research Society Bilateral Energy Conf., Nice, F, May 9-13, 2011
Grosse, M.; Stuckert, J.; Steinbrück, M.; Kaestner, A.
2011. European Materials Research Society Bilateral Energy Conf., Nice, F, May 9-13, 2011
Nitriding behavior of nickel-based superalloys at 1273 K and above
Grosse, M.; Sporn, M.; Menden, M.
2011. Internat.Congress on Advances in Nuclear Power Plants (ICAPP 2011), Nice, F, May 2-5, 2011 Proc.on CD-ROM Paper 11036 Paris : SFEN, 2011
Grosse, M.; Sporn, M.; Menden, M.
2011. Internat.Congress on Advances in Nuclear Power Plants (ICAPP 2011), Nice, F, May 2-5, 2011 Proc.on CD-ROM Paper 11036 Paris : SFEN, 2011
In-situ neutron radiography investigations of hydrogen diffusion and absorption in zirconium alloys
Grosse, M.; den Berg, M. van; Goulet, C.; Lehmann, E.; Schillinger, B.
2011. Nuclear Instruments and Methods in Physics Research A, 651, 253–257. doi:10.1016/j.nima.2010.12.070
Grosse, M.; den Berg, M. van; Goulet, C.; Lehmann, E.; Schillinger, B.
2011. Nuclear Instruments and Methods in Physics Research A, 651, 253–257. doi:10.1016/j.nima.2010.12.070
Wavelength dependent neutron transmission and radiography investigations of the high temperature behaviour of materials applied in nuclear fuel and control rod claddings
Grosse, M.; Steinbrück, M.; Kaestner, A.
2011. Nuclear Instruments and Methods in Physics Research A, 651, 315–319. doi:10.1016/j.nima.2011.02.102
Grosse, M.; Steinbrück, M.; Kaestner, A.
2011. Nuclear Instruments and Methods in Physics Research A, 651, 315–319. doi:10.1016/j.nima.2011.02.102