Institut für Angewandte Materialien - Angewandte Werkstoffphysik (IAM-AWP)

Publikationsliste


Preliminary validation of ASTEC V2.2.b with the QUENCH-20 BWR bundle experiment.
Murat, O.; Sanchez-Espinoza, V.; Wang, S.; Stuckert, J.
2020. Nuclear engineering and design, 370, 110931. doi:10.1016/j.nucengdes.2020.110931
Analysis of Options and Experimental Examination of Fuels for Water Cooled Reactors with Increased Accident Tolerance (ACTOF).
Cherubini, M.; Pastore, G.; Penttilä, S.; Ševeček, M.; Stuckert, J.; Veshchunov, M.; Xu, P.; Zozulia, I.
2020. International Atomic Energy Agency
Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions : Proceedings of a Technical Meeting.
Veshchunov, M.; Bouloré, A.; Liu, T.; Ševeček, M.; Stuckert, J.; Zhang, J.
2020. International Atomic Energy Agency
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
25 years QUENCH program. Main results of the QUENCH bundle tests.
Stuckert, J.; Große, M.; Steinbrück, M.
2019, Oktober 22. 25th International QUENCH Workshop (2019), Karlsruhe, Deutschland, 22.–24. Oktober 2019
First results of the QUENCH-20 test with BWR bundle.
Stuckert, J.; Große, M.; Laier, J.; Moch, J.; Peters, U.; Stegmaier, U.; Steinbrück, M.
2019, Oktober 22. 25th International QUENCH Workshop (2019), Karlsruhe, Deutschland, 22.–24. Oktober 2019
25 years QUENCH program. Highlights of separate-effects tests.
Steinbrück, M.; Stuckert, J.; Große, M.
2019, Oktober 22. 25th International QUENCH Workshop (2019), Karlsruhe, Deutschland, 22.–24. Oktober 2019. doi:10.5445/IR/1000100298
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
Experimental results of the bundle test QUENCH-19 with FeCrAl claddings.
Stuckert, J.; Große, M.; Steinbrück, M.; Terrani, K.
2019, Mai 17. ATF Topical Meeting (2019), Shenzhen, China, 16.–17. Mai 2019
The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test.
Kalilainen, J.; Lind, T.; Stuckert, J.; Bergfeldt, T.; Sippula, O.; Jokiniemi, J.
2019. Journal of nuclear materials, 517, 315–327. doi:10.1016/j.jnucmat.2019.02.021
Lessons learned from the QUENCH-LOCA experiments at KIT.
Stuckert, J.
2019, März 13. 23rd International Seminar ZIRAT on Zirconium Alloy Technology (2019), Palma de Mallorca, Spanien, 11.–13. März 2019
Post-test analyses of the CORA-15 bundle test with the system codes ATHLET-CD and SOCRAT.
Stuckert, J.; Austregesilo, H.; Bals, C.; Hollands, T.; Kiselev, A.; Tomashchik, D.; Yudina, T.
2019. Nuclear engineering and design, 342, 320–335. doi:10.1016/j.nucengdes.2018.12.015
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.; Stuckert, J.; Steinbrueck, M.; Fluhrer, B.; Keim, T.; Fischer, M.; Langrock, G.; Piluso, P.; Hozer, Z.; Kiselova, M.; Belloni, F.; Schyns, M.
2019. Annals of nuclear energy, 124, 541–547. doi:10.1016/j.anucene.2018.10.019
Fuel Modelling in Accident Conditions (FUMAC). Final Report of a Coordinated Research Project.
Boulore, A.; Chan, P.; Pastore, G.; Pizzocri, D.; Rathod, V.; Stuckert, J.; Van Uffelen, P.; Veshchunov, M.; Wiesenack, W.; Zhang, J.
2019. International Atomic Energy Agency
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
CoreSOAR Core Degradation State-of-the Art Report Update: Conclusions [in press].
Haste, T.; Barrachin, M.; Fichot, F.; Repetto; G.; Miassoedov, M.; Steinbrück, M.; Stuckert, J.; Buck, M.; Bechta, S.; Le Belguet, A.; Hollands, T.; Journeau, C.; Pontillon, Y.; Lind, T.; Birchley, J.; Hozer, Z.; Horvath, G. L.; Bottomley, P. D. W.
2019. 9th Conference on Severe Accident Research (ERMSAR2019), Prague, Czech Republic, March 18-20, 2019, paper 022
Coresoar core degradation soar update: summary.
Haste, T.; Barrachin, M.; Fichot, F.; Repetto, G.; Miassoedov, A.; Steinbrück, M.; Stuckert, J.; Buck, M.; Bechta, S.; Le Belguet, A.; Hollands, T.; Journeau, C.; Pontillon, Y.; Lind, T.; Birchley, J.; Hózer, Z.; Horvath, G. L.; Bottomley, P. D. W.
2019. The 9TH European Review Meeting on Severe Accident Research (ERMSAR2019), Prag, CZ, March 18-20, 2019
CLADS research for Fukushima Daiichi as contribution for the SAFEST Severe Accident Research Programme.
Kurata, M.; Okamoto, K.; Nagae, Y.; Bottomley, D.; Pshenichnikov, A.; Sudo, A.; Pham, H.; Bechta, S.; Stuckert, J.
2019. The 9TH European Review Meeting on Severe Accident Research (ERMSAR2019), Czech Republic, March 18-20, 2019
Pre- and Post-Test Simulations of the QUENCH-18 Bundle Experiment in the frame of the NUGENIA QUESA Project.
Hollands, T.; Bals, C.; Tiborcz, L.; Beuzet, E.; Vasiliev, A.; Kaliatka, T.; Birchley, J.; Steinbrück, M.; Stuckert, J.
2019. The 9TH European Review Meeting on Severe Accident Research (ERMSAR2019), Czech Republic, March 18-20, 2019, Paper 76
First aerosol results of the QUENCH-18 bundle test.
Kalilainen, J.; Lind, T.; Stuckert, J.; Stegmaier, U.
2019. 9th European Review Meeting on Severe Accident Research Severe Accident Research Conference (ERMSAR 2019), Prag, CZ, March 18-20, 2019, Paper 19
First results of the bundle test QUENCH-19 with FeCrAl claddings.
Stuckert, J.; Große, M.; Laier, J.; Moch, J.; Peters, U.; Stegmaier, U.; Steinbrück, M.; Terrani, K.
2018, November 13. 24th International Quench Workshop (2018), Karlsruhe, Deutschland, 13.–15. November 2018
First Results of the QUENCH-ALISA Bundle Test.
Stuckert, J.; Steinbrueck, M.; Kalilainen, J.; Lind, T.; Zhang, Y.
2018, Oktober 14. 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 2018), Qingdao, China, 14.–18. Oktober 2018
IAEA FUMAC Benchmark on the Halden, Studisvik and QUENCH-L1 LOCA tests.
Pizzocri, D.; Bouloré, A.; Stuckert, J.; Van Uffelen, P.; Wiesenack, W.; Zhang, J.
2018. TOPFUEL Reactor Fuel Performance, Prag, Czech Republic, 30 September - 04 October 2018, Paper A0222, ENS/TOPFUEL
IAEA FUMAC Benchmark on KIT Bundle Test CORA-15.
Stuckert, J.; Austregesilo, H.; Hollands, T. H.; Kiselev, A.
2018. TOPFUEL Reactor Fuel Performance, Prag, Czech Republic, 30 September - 04 October 2018, Paper A0202/1–16, ENS / TOPFUEL
FUMAC: IAEA’s Coordinated Research Project on Fuel Modelling in Accident Conditions.
Veshchunov, M.; Stuckert, J.; Van Uffelen, P.; Wiesenack, W.; Zhang, J.
2018. TOPFUEL Reactor Fuel Performance, Prag, Czech Republic, 30 September - 04 October 2018, Paper A0198, ENS / TOPFUEL
Update of the QUENCH program.
Steinbrueck, M.; Stuckert, J.; Grosse, M.
2018. 24th International Quench Workshop (2018), Karlsruhe, Deutschland, 13.–15. November 2018
Results of the QUENCH-DEBRIS (QUENCH-17) test with strongly oxidized Zircaloy-4 and Hafnium claddings filled with segmented pellet simulators.
Stuckert, J.; Große, M.; Onel, Y.; Rössger, C.; Stegmaier, U.; Steinbrück, M.
2018. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000088591
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
Summary of the QUENCH-LOCA : Experimental Program.
Wensauer, A.; Große, M.; Walter, M.; Stuckert, J.; Steinbrück, M.
2018. 49/49th Jahrestagung Kerntechnik / 49th Annual Meeting on Nuclear Technology (AMNT 2018), Berlin, Deutschland, 29.–30. Mai 2018
Results of the LOCA bundle test QUENCH-L5 with pre-hydrogenated optimised ZIRLO™ claddings (SR-7738).
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2018. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000083098
Results of the LOCA bundle test QUENCH-L4 with pre-hydrogenated M5® claddings (SR-7712).
Stuckert, J.; Große, M.; Pshenichnikov, A.; Rössger, C.; Steinbrück, M.; Walter, M.
2018. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000083094
Results of the LOCA bundle test QUENCH-L3 with optimised ZIRLO™ claddings (SR-7737).
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2018. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000083087
Results of the LOCA bundle test QUENCH-L2 with M5® claddings (SR-7677).
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2018. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000083069
Results of the LOCA reference bundle test QUENCH-L1 with Zircaloy-4 claddings (SR-7651).
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2018. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000083067
First results of the QUENCH-ALISA bundle test.
Stuckert, J.; Birchley, J.; Große, M.; Hollands, T.; Kalilainen, J.; Laier, J.; Lind, T.; Moch, J.; Peters, U.; Steinbrück, M.; Zhang, Y.
2017, Oktober 17. 23rd International QUENCH Workshop, Karlsruhe Institute of Technology, Karlsruhe, 17.-19.10.2017
Lessons learned from the QUENCH-LOCA experiments.
Stuckert, J.; Große, M.; Steinbrück, M.; Walter, M.; Wensauer, A.
2017, Oktober 17. 23rd International QUENCH Workshop, Karlsruhe Institute of Technology, Karlsruhe, 17.-19.10.2017
Core degradation and hydrogen source term during in-vessel accident scenarios - Results from the QUENCH program at KIT.
Steinbrück, M.; Stuckert, J.; Große, M.
2017, Juli 6. CLADS workshop, July 5-6 , 2017, Tomioka, Fukushima, J
UK Research in LOCA-Related Activities and Co-operation with the Karlsruhe Research Centre - A Historical Perspective.
Lillington, J.; Walker, S.; Steinbrück, M.; Stuckert, J.
2017. 23rd International QUENCH Workshop, Karlsruhe Institute of Technology, Karlsruhe, Germany, 17.-19.10.2017
Update of the QUENCH program.
Steinbrück, M.; Stuckert, J.; Große, M.
2017. 23rd International QUENCH Workshop, Karlsruhe Institute of Technology, Karlsruhe, Germany, 17.-19.10.2017
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.; Fluhrer, B.; Miassoedov, A.; Stuckert, J.; Steinbrueck, M.; Bechta, S.; Kudinov, P.; Ma, W. M.; Sehgal, B. R.; Hozer, Z.; Guba, A.; Manara, D.; Bottomley, D. P.; Fischer, M.; Langrock, G.; Schmidt, H.; Kiselova, M.; Zdarek, J.
2017. Journal of risk and uncertainty, 4 (3), Art.Nr. 030901. doi:10.1115/1.4037878
Validation of ASTECV2.1 based on the QUENCH-08 experiment.
Gómez-García-Toraño, I.; Sánchez-Espinoza, V.-H.; Stieglitz, R.; Stuckert, J.; Laborde, L.; Belon, S.
2017. Nuclear engineering and design, 314, 29–43. doi:10.1016/j.nucengdes.2016.12.039
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.; Fluhrer, B.; Miassoedov, A.; Stuckert, J.; Steinbrück, M.; Bechta, S.; Kudinov, P.; Hozer, Z.; Guba, A.; Manara, D.; Bottomley, D.; Fischer, M.; Langrock, G.; Schmidt, H.; Kiselova, M.; Ždarek, J.
2016. 2016 24th International Conference on Nuclear Engineering, Charlotte, North Carolina, USA, 26 June 2016, V004T14A019, American Society of Mechanical Engineers (ASME). doi:10.1115/ICONE24-60916
Orientation relationships of delta hydrides in zirconium and Zircaloy-4.
Pshenichnikov, A.; Stuckert, J.
2016. 24th International Conference on Nuclear Engineering, ICONE 2016; Charlotte; United States; 26 June 2016 through 30 June 2016. Volume 1, V001T02A006, American Society of Mechanical Engineers (ASME). doi:10.1115/ICONE24-60061
Land contamination activity data interpretation from Fukushima Daiichi accident.
Jäckel, B. S.; Bevilacqua, A.; Ducros, G.; Gauntt, R.; Stuckert, J.
2016. Nuclear engineering and design, 300 (2016), 28–33. doi:10.1016/j.nucengdes.2015.12.030
First results of the bundle test QUENCH-L5 with pre-hydrogenated opt. ZIRLO™ claddings.
Stuckert, J.; Große, M.; Moch, J.; Rössger, C.; Steinbrück, M.; Walter, M.
2016. 22nd International QUENCH Workshop, 18-22 October 2016, Karlsruhe Institute of Technology, Karlsruhe, Germany
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
The QUENCH Program at KIT.
Steinbrück, M.; Stuckert, J.; Grosse, M.
2016. KNF Seminar, KEPCO Nuclear Fuel, 01. November 2016, Daejoen, Korea
Orientation relationships of delta hydrides in zirconium and zircaloy-4.
Pshenichnikov, A.; Stuckert, J.
2016. 24th International Conference on Nuclear Engineering (ICONE24), Charlotte, N.C., June 26-30, 2016. Proceedings on CD-ROM, ICONE24–60061, American Society of Mechanical Engineers (ASME)
Orientation relationships of δ-hydrides in zirconium and zircaloy-4.
Pshenichnikov, A.; Stuckert, J.
2016. 26th International Conference on Nuclear Engineering (ICONE 2018), London, Vereinigtes Königreich, 22.–28. Juli 2018
Safest roadmap for corium experimental research in Europe.
Journeau, C.; Bouyer, V.; Cassiaut-Louis, N.; Fouquart, P.; Piluso, P.; Ducros, G.; Gosse, S.; Gueneau, C.; Quaini, A.; Fluhrer, B.; Miassoedov, A.; Stuckert, J.; Steinbrück, M.; Bechta, S.; Kudinov, P.; Hozer, Z.; Guba, A.; Manara, D.; Bottomley, D.; Langrock, G.; Schmidt, H.; Kiselova, M.; Zdarek, J.
2016. 24th International Conference on Nuclear Engineering (ICONE24), Charlotte, NC, June 26-30, 2016. Proceedings on CD-ROM, ICONE24–60916, American Society of Mechanical Engineers (ASME)
Safest roadmap for corium experimental research in Europe.
Journeau, C.; Bouyer, V.; Cassiaut-Louis, N.; Fouquart, P.; Piluso, P.; Ducros, G.; Gosse, S.; Gueneau, C.; Quaini, A.; Fluhrer, B.; Miassoedov, A.; Stuckert, J.; Steinbrück, M.; Bechta, S.; Kudinov, P.; Hozer, Z.; Guba, A.; Manara, D.; Bottomley, D.; Langrock, G.; Schmidt, H.; Kiselova, M.; Zdarek, J.
2016. 26th International Conference on Nuclear Engineering (ICONE 2018), London, Vereinigtes Königreich, 22.–28. Juli 2018
Application of thermal hydraulic and severe accident cde SOCRAT/V3 to bottom water reflood experiment QUENCH-LOCA-1.
Vasiliev, A.; Stuckert, J.
2016. Journal of Nuclear Engineering and Radiation Science, 2, 021024/1–7. doi:10.1115/1.4031815
Cladding oxidation during air ingress. Part I: Experiments on air ingress.
Stuckert, J.; Hozer, Z.; Kiselev, A.; Steinbrück, M.
2016. Annals of Nuclear Energy, 93, 4–17. doi:10.1016/j.anucene.2015.12.034
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
Results of the commissioning bundle test QUENCH-L0 performed under LOCA conditions. (SR-7571).
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2015. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000083018
Post-test investigations of the Quench-Loca-4 bundle (hydrogenated M5(Registered) claddings).
Stuckert, J.; Große, M.; Pshenichnikov, A.; Rössger, C.; Walter, M.
2015. 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015
First results of the bundle test QUENCH-L3 with optimized ZIRLO™ claddings.
Stuckert, J.; Große, M.; Moch, J.; Rössger, C.; Steinbrück, M.; Walter, M.
2015. 21st International Quench Workshop (2015), Karlsruhe, Deutschland, 27.–29. Oktober 2015
Orientation relationships of δ-hydrides in Zirconium and Zircaloy-4.
Pshenichnikov, A.; Stuckert, J.; Walter, M.
2015. 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015
Update of the Quench programme.
Steinbrück, M.; Stuckert, J.; Große, M.
2015. 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015
Update of the Quench programme.
Steinbrück, M.; Stuckert, J.; Große, M.
2015. Steinbrück, M. [Hrsg.] Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015, Karlsruher Institut für Technologie (KIT)
Cladding oxidation during air ingress. Part I: Experiments on air ingress.
Stuckert, J.; Hozer, Z.; Kiselev, A.; Steinbrück, M.
2015. 7th Conference on Severe Accident Research (ERMSAR 2015), Marseille, F, March 24-26, 2015
Cladding oxidation during air ingress. Part I: Experiments on air ingress.
Stuckert, J.; Hozer, Z.; Kiselev, A.; Steinbrück, M.
2015. 7th Conference on Severe Accident Research (ERMSAR 2015), Marseille, F, March 24-26, 2015. Proceedings, Paper 038bis
First results of the bundle test Quench-L3 with optimized Zirlosup(T)sup(M) claddings.
Stuckert, J.; Große, M.; Moch, J.; Rössger, C.; Steinbrück, M.; Walter, M.
2015. Steinbrück, M. [Hrsg.] Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015, Karlsruher Institut für Technologie (KIT)
Post-test investigations of the Quench-Loca-4 bundle (hydrogenated M5(Registered) claddings).
Stuckert, J.; Große, M.; Pshenichnikov, A.; Rössger, C.; Walter, M.
2015. Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)
Orientation relationships of δ-hydrides in Zirconium and Zircaloy-4.
Pshenichnikov, A.; Stuckert, J.; Walter, M.
2015. Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)
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
Hydrides and fracture of pure zirconium and zircaloy-4 hydrogenated at temperatures typical for loss-of-coolant accident conditions.
Pshenichnikov, A.; Stuckert, J.; Walter, M.; Litvinov, D.
2015. 23rd International Conference on Nuclear Engineering (ICONE23), Chiba, J, May 17-21, 2015
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
Hydrides and fracture of pure zirconium and zircaloy-4 hydrogenated at temperatures typical for loss-of-coolant accident conditions.
Pshenichnikov, A.; Stuckert, J.; Walter, M.; Litvinov, D.
2015. 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015; Makuhari MesseChiba, Japan, 17 - 21 May 2015. Proceedings, Paper ICONE23–1724, American Society of Mechanical Engineers (ASME)
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
Integration of new experiments into the reflood map.
Hering, W.; Homann, C.; Stuckert, J.
2015. International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, F, May 3-6, 2015
Integration of new experiments into the reflood map.
Hering, W.; Homann, C.; Stuckert, J.
2015. International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, F, May 3-6, 2015, 1420–1428, Omnipress
Analysis of the secondary cladding hydrogenation during the QUENCH-LOCA bundle tests with zircaloy-4 claddings and its influence on the cladding embrittlement.
Große, M.; Stuckert, J.; Rössger, C.; Steinbrück, M.; Walter, M.; Kaestner, A.
2015. 17th International Symposium on Zirconium in the Nuclear Industry; Hyderabad, Andhra Pradesh; India, 3 February 2013 - 7 February 2013 Ed.: R. J. Comstock, 1054–1073, ASTM International. doi:10.1520/STP154320120155
First results of the high temperature bundle test QUENCH-L3HT with optimized ZIRLOsup(T)sup(M) claddings.
Stuckert, J.; Große, M.; Moch, J.; Rössger, C.; Steinbrück, M.; Walter, M.
2014. Proceedings of the 20th International QUENCH Workshop, Karlsruhe, November 11-13, 2014. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)
Update of the QUENCH programme.
Steinbrück, M.; Stuckert, J.; Große, M.
2014. Proceedings of the 20th International QUENCH Workshop, Karlsruhe, November 11-13, 2014. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)
Update of the QUENCH programme.
Steinbrück, M.; Stuckert, J.; Große, M.
2014. 20th International QUENCH Workshop, Karlsruhe, November 11-13, 2014
First results of the high temperature bundle test QUENCH-L3HT with optimized ZIRLOsup(T)sup(M) claddings.
Stuckert, J.; Große, M.; Moch, J.; Rössger, C.; Steinbrück, M.; Walter, M.
2014. 20th International QUENCH Workshop, Karlsruhe, November 11-13, 2014
Influence of the temperature history on secondary hydriding and mechanical properties of zircaloy-4 claddings. An analysis of the QUENCH-LOCA bundle test.
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2014. 22nd International Conference on Nuclear Engineering (ICONE22), Praha, CZ, July 7-11, 2014
Influence of the temperature history on secondary hydriding and mechanical properties of zircaloy-4 claddings. An analysis of the QUENCH-LOCA bundle test.
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2014. 22nd International Conference on Nuclear Engineering (ICONE22), Praha, CZ, July 7-11, 2014, Paper ICONE22–30792, American Society of Mechanical Engineers (ASME)
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
Results of the QUENCH-DEBRIS test.
Stuckert, J.; Große, M.; Onel, Y.; Rössger, C.; Steinbrück, M.
2014. International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Charlotte, N.C., April 6-9, 2014
Results of the QUENCH-DEBRIS test.
Stuckert, J.; Große, M.; Onel, Y.; Rössger, C.; Steinbrück, M.
2014. International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Charlotte, N.C., April 6-9, 2014. Vol. 2, 1123–1128, American Nuclear Society
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
Experimental results of the QUENCH-16 bundle test on air ingress.
Stuckert, J.; Steinbrück, M.
2014. Progress in nuclear energy, 71, 134–141. doi:10.1016/j.pnucene.2013.12.001
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
Update of the QUENCH programme.
Steinbrück, M.; Stuckert, J.; Große, M.
2013. 19th International QUENCH Workshop, Karlsruhe, November 19-21, 2013
Update of the QUENCH programme.
Steinbrück, M.; Stuckert, J.; Große, M.
2013. Proceedings of the 19th International QUENCH Workshop, Karlsruhe, November 19-21, 2013. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)
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
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
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
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
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
QUENCH-LOCA program at KIT on secondary hydriding and results of the commissioning bundle test QUENCH-L0.
Stuckert, J.; Große, M.; Rössger, C.; Klimenkov, M.; Steinbrück, M.; Walter, M.
2013. Nuclear Engineering and Design, 255, 185–201. doi:10.1016/j.nucengdes.2012.10.024
First results of the QUENCH-17 bundle test on debris formation.
Stuckert, J.; Moch, J.; Rössger, C.; Steinbrück, M.; Große, M.
2013. SARNET2: WP5-COOL Review Meeting, Fuertaventura, E, February 11-14, 2013
Results of the QUENCH-16 Bundle Experiment on Air Ingress (KIT Scientific Reports ; 7634).
Stuckert, J.; Große, M.; Hózer, Z.; Steinbrück, M.
2013. KIT Scientific Publishing. doi:10.5445/KSP/1000034168
Analysis of the secondary hydrogenation during the QUENCH-LOCA bundle tests with Zry-4 claddings and its influence on the cladding embrittlement.
Große, M.; Stuckert, J.; Rössger, C.; Steinbrück, M.; Walter, M.; Kaestner, A.
2013. 17th Internat.Symp.on Zirconium in the Nuclear Industry, Hyderabad, IND, February 3-7, 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
Overview of LWR severe accident research activities at the Karlsruhe Institute of Technology.
Miassoedov, A.; Albrecht, G.; Foit, J. J.; Jordan, T.; Steinbrück, M.; Stuckert, J.; Tromm, W.
2012. 14th Brazilian Congress of Thermal Sciences and Engineering (ENCIT 2012), Rio de Janeiro, BR, November 18-22, 2012
Overview of LWR severe accident research activities at the Karlsruhe Institute of Technology.
Miassoedov, A.; Albrecht, G.; Foit, J. J.; Jordan, T.; Steinbrück, M.; Stuckert, J.; Tromm, W.
2012. Proc.of 14th Brazilian Congress of Thermal Sciences and Engineering (ENCIT 2012), Rio de Janeiro, BR, November 18-22, 2012, Associacao Brasileira de Engenharia e Ciencias Mecanicas (ABCM)
Update of the QUENCH programme.
Steinbrück, M.; Stuckert, J.; Große, M.
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
Results of the reference bundle test QUENCH-L1 with Zircaloy-4 claddings and future planning of the QUENCH-LOCA program.
Stuckert, J.; Rössger, C.; Walter, M.; Große, M.; Steinbrück, M.
2012. Proc.of the 18th Internat.QUENCH Workshop, Karlsruhe, November 20-22, 2012. Hrsg.: M. Steinbrück, CD-ROM, Karlsruher Institut für Technologie (KIT)
Post-test results of the QUENCH-16 bundle test on air ingress: complex cladding oxidation during reflood and combined hydrogen.
Stuckert, J.; Steinbrück, M.
2012. Proc.of the 18th Internat.QUENCH Workshop, Karlsruhe, November 20-22, 2012. Hrsg.: Steinbrück, CD-ROM, Karlsruher Institut für Technologie (KIT)
Update of the QUENCH programme.
Steinbrück, M.; Stuckert, J.; 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)
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)
Results of the reference bundle test QUENCH-L1 with Zircaloy-4 claddings and future planning of the QUENCH-LOCA program.
Stuckert, J.; Rössger, C.; Walter, M.; Große, M.; Steinbrück, M.
2012. 18th Internat.QUENCH-Workshop, Karlsruhe, November 20-22, 2012
Post-test results of the QUENCH-16 bundle test on air ingress: complex cladding oxidation during reflood and combined hydrogen.
Stuckert, J.; Steinbrück, M.
2012. 18th Internat.QUENCH-Workshop, Karlsruhe, November 20-22, 2012
High-temperature oxidation and mutual interactions of materials during severe nuclear accidents.
Steinbrück, M.; Große, M.; Stuckert, J.
2012. Nuclear Materials Conf. (NuMat 2012), Osaka, J, October 22-25, 2012
Experimental results of the QUENCH-16 bundle test on air ingress.
Stuckert, J.; Steinbrück, M.
2012. Internat.Congress on the Advances in Nuclear Power Plants (ICAPP 12), Chicago, Ill., June 24-28, 2012, CD-ROM, American Nuclear Society
QUENCH-LOCA program at KIT and results of the QUENCH-L0 bundle test.
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2012. Jahrestagung Kerntechnik 2012, Stuttgart, 22.-24.Mai 2012, CD-ROM, INFORUM
Experimental results of the QUENCH-16 bundle test on air ingress.
Stuckert, J.; Steinbrück, M.
2012. Internat.Congress on the Advances in Nuclear Power Plants (ICAPP 12), Chicago, Ill., June 24-28, 2012
Application of neutron radiography to study material processes during hypothetical severe accidents in nuclear reactors.
Große, M.; Steinbrück, M.; Stuckert, J.; Kastner, A.; Schillinger, B.
2012. Journal of Materials Science, 47, 6505–6512. doi:10.1007/s10853-011-5553-1
Separate effects experiments in the framework of the QUENCH program at KIT.
Steinbrück, M.; Große, M.; Stuckert, J.
2012. Final Seminar of the Phebus Programme, Aie-en-Provence, F, June 13-15, 2012
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
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
QUENCH-LOCA program at KIT and results of the QUENCH-L0 bundle test.
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2012. Jahrestagung Kerntechnik 2012, Stuttgart, 22.-24.Mai 2012
QUENCH-LOCA program at KIT and results of the QUENCH L0 bundle test.
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2012. LOCA-Workshop, Lyon, F, May 29-30, 2012
Modeling of QUENCH-16 experiment with MAAP4 severe accident code.
Beuzet, E.; Steinbrück, M.; Stuckert, J.
2012. Topical Meeting on Safety in Reactor Operations (TopSafe 2012), Helsinki, SF, April 22-26, 2012
Modeling of QUENCH-16 experiment with MAAP4 severe accident code.
Beuzet, E.; Steinbrück, M.; Stuckert, J.
2012. Topical Meeting on Safety in Reactor Operations (TopSafe 2012 Transactions), Helsinki, SF, April 22-26, 2012, 265–271, European Nuclear Society
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
Experimental results of the QUENCH-16 bundle tests on air ingress, performed within the framework of the LACOMECO project.
Stuckert, J.; Hozer, Z.; Moch, J.; Rössger, C.; Stegmaier, U.; Steinbrück, 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
Update of the QUENCH program.
Steinbrück, M.; Stuckert, J.; Große, M.; Walter, M.
2011. 17th Internat.QUENCH-Workshop, Karlsruhe, November 22-24, 2011
Verhalten von Hüllrohrmaterialien bei Large Break LOCA (QUENCH-LOCA test series).
Steinbrück, M.; Stuckert, J.; Große, M.; Walter, M.
2011. Workshop ’Status VGB Schwerpunktförderung’, E.ON Hannover, 27.Oktober 2011
Update of the QUENCH program.
Steinbrück, M.; Stuckert, J.; Große, M.; Walter, 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
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
Experimental results of the QUENCH-16 bundle tests on air ingress, performed within the framework of the LACOMECO project.
Stuckert, J.; Hozer, Z.; Moch, J.; Rössger, C.; Stegmaier, U.; Steinbrück, M.
2011. 17th Internat.QUENCH-Workshop, Karlsruhe, November 22-24, 2011
Experimental results of the commissioning bundle test QUENCH-L0 performed in the framework of the QUENCH-LOCA program.
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2011. Internat.Congress on Advances in Nuclear Power Plants (ICAPP 2011), Nice, F, May 2-5, 2011 Proc.on CD-ROM Paper 11226 Paris : SFEN, 2011
QUENCH-LOCA program at KIT and results of the QUENCH L0 bundle test.
Stuckert, J.; Große, M.; Steinbrück, M.; Walter, M.
2011. HI Temp Conf.2011, Boston, Mass., September 20-22, 2011
Experimental results of the commissioning bundle test QUENCH-L0 performed in the framework of the QUENCH-LOCA program.
Stuckert, J.; Große, M.; Rössger, C.; Steinbrück, M.; Walter, M.
2011. Internat.Congress on Advances in Nuclear Power Plants (ICAPP 2011), Nice, F, May 2-5, 2011
Results of Severe Fuel Damage Experiment QUENCH-15 with ZIRLO cladding tubes. (KIT Scientific Reports ; 7576).
Stuckert, J.; Große, M.; Stegmaier, U.; Steinbrück, M.
2011. KIT Scientific Publishing. doi:10.5445/KSP/1000022788
Mechanical properties of pre-hydrogenated (600 - 5000 wppm) cladding segments.
Stuckert, J.; Große, M.; Walter, M.
2010. Steinbrück, M. [Hrsg.] Proc.of the 16th Internat.QUENCH Workshop, Karlsruhe, November 16-18, 2010 CD-ROM Karlsruhe : Karlsruhe Inst.of Technology, Campus North, 2010 urn:nbn:de:0005-900101, 16th International QUENCH Workshop (2010), Karlsruhe, Deutschland, 16.–18. November 2010
Experimental investigation of the late phase of spent fuel pool accidents.
Kunstar, M.; Matus, L.; Ver, N.; Pinter, A.; Hozer, Z.; Steinbrück, M.; Stuckert, J.
2007. International journal of nuclear energy science and technology, 3 (3), 287. doi:10.1504/IJNEST.2007.016667
ZRO₂ and UO₂ dissolution by molten Zircalloy.
Stuckert, J.; Miassoedov, A.; Hayward, P. J.; Hofmann, P.; Veshchunov, M.
2002. Proceedings of the International Conference Nuclear Energy for New Europe 2002 (NENE 2002), Kranjska Gora, SLO, September 9-12, 2002. Ed.: I. Jencic, 251–258, Nuclear Society of Slovenia