Forschungsthemen
- Wir verfügen über eine große Expertise auf dem Gebiet der Oxidation von Zirkoniumlegierungen in verschiedenen Atmosphären (Wasserdampf, Luft, Sauerstoff, Stickstoff, Mischungen dieser) im Temperaturbereich 600-1600 °C sowie der Wechselwirkung von Wasserstoff mit Zirkonium.
- Neutronenradiographie und –tomographie werden u.a. zur Untersuchung des Verhaltens von Wasserstoff in Metallen in Zusammenarbeit mit verschiedenen Neutronenquellen angewendet. Ein Anwendungsgebiet dafür ist die Langzeitzwischenlagerung von abgebrannten Brennelementen in trockenen Zwischenlagern (CASTOR Behältern).
- Unser Labor ist weltweit anerkannt für die Qualifizierung von neuen, unfalltoleranten Hüllrohrmaterialien bis zu sehr hohen Temperaturen von 2000°C (ATF=Accident Tolerant Fuel).
Versuchstechnik
- Hochtemperatur Thermowaage Netzsch STA 449 mit Dampfofen und MS-Kopplung
- Setaram High Performance symmetrisches TGA System bis 1700 °C
- Verschiedene Hochtemperaturöfen (Widerstandsheizung, induktive Heizung) für Reaktionen in definierten Atmosphären (Luft, Sauerstoff, Stickstoff, Wasserstoff, Wasserdampf etc.) bis 1600 °C und in inerter Atmosphäre bis 2300 °C.
- Analyse von gasförmigen Reaktionsprodukten mittels Massenspektrometrie im Prozent- und ppm-Bereich (IPI GAM3000).
- INRRO Anlage zur in-situ Analyse von Wasserstoffabsorption und -diffusion in Zirkoniumlegierungen mittels Neutronenradiographie.
- Einzelstab-Versuchsanlage QUENCH-SR mit Abschreckvorrichtungen.
- QUENCH-Anlage für Bündelversuche zum Abschrecken eines überhitzten Reaktorkerns (bei und zusammen betrieben mit Gruppe Nukleare Sicherheitsforschung)
- Metallographisches Labor, Lichtmikroskopie, REM-EDX
Kooperationen
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CSARP (Cooperative Severe Accident Research Program der US Nuclear Regulatory Commission)
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EC Research Program IL TROVATORE (Innovative cladding materials for advanced accident-tolerant energy systems)
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IAEA Cooperative Research Program on Testing and Simulation of Advanced Technology Fuels (ATF-TS)
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OECD-NEA activities on ATF cladding materials QUENCH-ATF and TOPATF
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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)
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BMWi Projekt SPIZWURZ (Spannungsinduzierte Wasserstoffumlagerung in Brennstabhüllrohren während längerfristiger Zwischenlagerung)
Publikationen
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, LaGrange Park (IL)
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, LaGrange Park (IL)
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, LaGrange Park (IL)
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, LaGrange Park (IL)
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, ANS, LaGrange Park (IL)
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, ANS, LaGrange Park (IL)
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, LaGrange Park
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, LaGrange Park
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, LLC
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, LLC
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-SiC CMC cladding tubes for GFR application in impure helium atmosphere and materials interactions with tantalum liner at high temperatures up to 1600°C.
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. KIT, Karlsruhe. doi:10.5445/IR/1000091676
Tang, C.
2019. KIT, Karlsruhe. 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 Associates, Inc., Red Hook, NY
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 Associates, Inc., Red Hook, NY
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, IEEE, Piscataway, NJ. 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, IEEE, Piscataway, NJ. 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 2 AlC-coated Zircaloy-4.
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, West Conshohocken (PA). 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, West Conshohocken (PA). 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, Vienna
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, Vienna
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, Tokyo
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, Tokyo
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, LaGrange Park (IL)
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, LaGrange Park (IL)
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, LaGrange Park, Illinois
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, LaGrange Park, Illinois
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, La Grange Park (Ill.)
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, La Grange Park (Ill.)
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, LaGrange Park (IL)
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, LaGrange Park (IL)
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, KIT-CN, Karlsruhe
Grosse, M.
2015. Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015. Hrsg.: M. Steinbrück, KIT-CN, Karlsruhe
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, KIT-CN, Karlsruhe
Grosse, M.; Roessger, C.; Muttini, E.
2015. Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015. M. Steinbrück, KIT-CN, Karlsruhe
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, KIT Campus Nord, Karlsruhe
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, KIT Campus Nord, Karlsruhe
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.; de Luze, O.; 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.; de Luze, O.; 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, Madison, WI
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, Madison, WI
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, Conshocken, Pa. 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, Conshocken, Pa. 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, Karlsruhe Institute of Technology, Campus North, Karlsruhe
Grosse, M.
2013. Proceedings of the 19th International QUENCH Workshop, Karlsruhe, November 19- 21, 2013. Hrsg.: M. Steinbrück, Karlsruhe Institute of Technology, Campus North, Karlsruhe
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, Karlsruhe Institute of Technology, Campus North, Karlsruhe
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, Karlsruhe Institute of Technology, Campus North, Karlsruhe
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, La Grange Park, Ill
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, La Grange Park, Ill
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, La Grange Park, Ill
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, La Grange Park, Ill
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.; de Luze, O.; 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, Ljubljana, SLO
Haste, T.; Steinbrück, M.; Barrachin, M.; de Luze, O.; 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, Ljubljana, SLO
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.; de Luze, O.; 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.; de Luze, O.; 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, Warrendale, PA. 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, Warrendale, PA. 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, KIT, Karlsruhe
Prestel, S.; Grosse, M.
2012. Proc.of the 18th Internat.QUENCH Workshop, Karlsruhe, November 20-22, 2012. Hrsg.: M. Steinbrück, CD-ROM, KIT, Karlsruhe
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, KIT, Karlsruhe
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, KIT, Karlsruhe
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, KIT, Karlsruhe
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, KIT, Karlsruhe
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.; van den Berg, M.; Goulet, C.; Kaestner, A.
2012. Journal of Physics: Conference Series, 340, 0012106/1–8. doi:10.1088/1742-6596/340/1/012106
Grosse, M.; van den Berg, M.; 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.; van den Berg, M.; Kaestner, A.; Schillinger, B.
2011. 5th European Conf.on Neutron Scattering (ECNS 2011), Praha, CZ, July 17-22, 2011
Grosse, M.; van den Berg, M.; 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.; van den Berg, M.; 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.; van den Berg, M.; 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