Publikationsliste

Modelling the morphology of hydrides in fuel rod cladding under the conditions of the long-term bundle test in the framework of the SPIZWURZ project
Kolesnik, M.; Stuckert, J.; Grosse, M.
2024. Proceedings of TopFuel 2024, Grenoble, 29th September - 3rd October 2024, paper 35

Investigations of the SPIZWURZ bundle after the 250 day-long dry-storage simulation
Weick, S.; Grosse, M.; Roessger, C.; Stuckert, J.
2024. Proceedings of TopFuel 2024, Article no: 166

Experimental programme within the IAEA ATF-TS - separate effect and bundle tests with ATF cladding materials
Ševeček, M.; Stuckert, J.; Sim, K.; Khaperskaia, A.
2024. TopFuel 2024 Reactor Fuel Performance : 29 September-3 October 2024, Grenoble, France, paper 235

Behavior of bundles with Cr coated claddings under BDBA conditions at the DEGREE facility
Nakamura, K.; Inagaki, K.; Stuckert, J.; Ševeček, M.; Tarumi, N.
2024. TopFuel 2024 Reactor Fuel Performance : 29 September-3 October 2024, Grenoble, France, paper 261

IAEA ATF-TS Benchmark for simulation of bundle tests
Stuckert, J.; Hózer, Z.; Khaperskaia, A.; Sim, K.
2024. Proceedings of TopFuel 2024, Article no: 119

OECD-NEA Joint Undertaking QUENCH-ATF
Stuckert, J.; Steinbrück, M.; Tromm, T. W.
2023. NEA Nuclear Safety Joint Projects Week (2023), Online, January 9–13, 2023

Initial assessment of MELCOR Nitriding Model using Air Ingress Experiments QUENCH-16 and QUENCH-18
Birchley, J.; Stuckert, J.; Steinbrück, M.
2024. doi:10.5445/IR/1000170208

An Overview of Mechanisms of the Degradation of Promising ATF Cladding Materials During Oxidation at High Temperatures
Steinbrueck, M.; Grosse, M.; Tang, C.; Stuckert, J.; Seifert, H. J.
2024. High Temperature Corrosion of Materials, 101 (4), 621–647. doi:10.1007/s11085-024-10229-y

Advancing the State of the Practice in Uncertainty and Sensitivity Methodologies for Severe Accident Analysis in Water Cooled Reactors in the QUENCH-06 Experiment
International Atomic Energy Agency (IAEA)Advancing the State of the Practice in Uncertainty and Sensitivity Methodologies for Severe Accident Analysis in Water Cooled Reactors in the QUENCH-06 Experiment
2024

Hydrogenation of claddings in the new developed HOKI oven and performance of the long-term bundle test under dry storage conditions in the framework of the SPIZWURZ project
Stuckert, J.; Rössger, C.; Moch, J.; Grosse, M.; Weick, S.
2023, December 5. 28th International QUENCH Workshop (2023), Karlsruhe, Germany, December 5–7, 2023

Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs
Joung, S.; Kim, J.; Ševeček, M.; Stuckert, J.; Lee, Y.
2024. Journal of Nuclear Materials, 591, Article no: 154915. doi:10.1016/j.jnucmat.2024.154915

The SPIZWURZ project – Experimental investigations and modeling of the behavior of hydrogen in zirconium alloys under long-term dry storage conditions
Grosse, M.; Boldt, F.; Herm, M.; Roessger, C.; Stuckert, J.; Weick, S.; Nahm, D.
2024. Nuclear Engineering and Technology, 56, 824–831. doi:10.1016/j.net.2023.09.027

KIT reactor safety research for LWRs: Research lines, numerical tools, and prospects
Sanchez-Espinoza, V. H.; Gabrielli, F.; Imke, U.; Zhang, K.; Mercatali, L.; Huaccho, G.; Duran, J.; Campos, A.; Stakhanova, A.; Murat, O.; Mercan, A. K.; Etcheto, J.; Steinbrück, M.; Stuckert, J.; Gabriel, S.; Ottenburger, S.; Stieglitz, R.; Tromm, W.
2023. Nuclear Engineering and Design, 414, Art.-Nr.: 112573. doi:10.1016/j.nucengdes.2023.112573

KIT Computational Route for the Safety Assessment and Radiological Risk Prediction of NPPs
Sánchez-Espinoza, V. H.; Gabrielli, F.; Zhang, K.; Mercatali, L.; Imke, U.; Steinbrück, M.; Stuckert, J.; Gabriel, S.; Ottenburger, S.; Stieglitz, R.; Tromm, W.
2023. RSK-AST Meeting (2023), Online, May 11, 2023

Experimental and modelling results of the QUENCH-20 experiment with BWR test bundle
Stuckert, J.; Bechta, S.; Hollands, T.; Isaksson, P.; Steinbrueck, M.
2023. Nuclear Engineering and Design, 410, Article no: 112391. doi:10.1016/j.nucengdes.2023.112391

Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment
Doyle, P.; Stuckert, J.; Grosse, M.; Steinbrück, M.; Nelson, A. T.; Harp, J.; Terrani, K.
2023. Journal of Nuclear Materials, 580, Article no: 154433. doi:10.1016/j.jnucmat.2023.154433

Limiting degradation mechanisms for high-temperature oxidation resistance of promising ATF cladding solutions
Steinbrück, M.; Große, M.; Tang, C.; Stuckert, J.
2022. Proceedings | TopFuel 2022 Light Water Reactor Fuel Performance Conference | Raleigh, NC, October 9-13, 2022, 251–260, American Nuclear Society (ANS). doi:10.13182/TopFuel22-38967

Results of metallographic analysis of the QUENCH-20 bundle with B₄C absorber
Stuckert, J.; Peters, U.; Stegmaier, U.; Steinbrück, M.
2022, May 18. 10th European Review Meeting on Severe Accident Research (ERMSAR 2022), Karlsruhe, Germany, May 16–19, 2022

Results of metallographic analysis of the QUENCH-20 bundle with B4C absorber
Stuckert, J.; Peters, U.; Stegmaier, U.; Steinbrück, M.
2022. Proceedings of the 10th European Review Meeting on Severe Accidents Research (ERMSAR2022), 1308–1318, Karlsruher Institut für Technologie (KIT)

Results of the QUENCH-20 experiment with BWR test bundle
Stuckert, J.; Bechta, S.; Große, M.; Isaksson, P.; Laier, J.; Moch, J.; Peters, U.; Stegmaier, U.; Steinbrück, M.
2022. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000149400

Effect of steam and oxygen starvation on severe accident progression with air ingress
Farkas, R.; Hózer, Z.; Nagy, I.; Vér, N.; Horváth, M.; Steinbrück, M.; Stuckert, J.; Grosse, M.
2022. Nuclear Engineering and Design, 396, 111884. doi:10.1016/j.nucengdes.2022.111884

Results of the bundle test QUENCH-19 with FeCrAl claddings
Stuckert, J.; Grosse, M.; Steinbrück, M.
2022. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000148370

Single rod tests at KIT with Cr coated claddings
Stuckert, J.; Stegmaier, U.; Vizelkova, K.
2021, August 25. 1st Research Coordination Meeting on Testing, Modelling and Simulations for Accident Tolerant and Advanced Technology Fuels (2021), Online, August 23–27, 2021

Current Severe Accident Researches in Germany
Gaus-Liu, X.; Stuckert, J.
2021. 28th International Conference on Nuclear Engineering (ICONE 2021), Online, August 4–6, 2021

Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release
Stuckert, J.; Steinbrueck, M.; Kalilainen, J.; Lind, T.; Birchley, J.
2021. Nuclear engineering and design, 379, Art.-Nr.: 111267. doi:10.1016/j.nucengdes.2021.111267

Results of the QUENCH-18 Bundle Experiment on Air Ingress and AgInCd absorber behavior
Stuckert, J.; Kalilainen, J.; Lind, T.; Stegmaier, U.; Steinbrück, M.; Zhang, Y.
2020. Karlsruher Institut für Technologie (KIT). doi:10.5445/IR/1000131350

Hafnium Oxidation at High Temperature in Steam
Guilbert-Banti, S.; Viretto, A.; Barrachin, M.; Tanguy, C.; Steinbrück, M.; Stuckert, J.
2021. Journal of nuclear materials, 550, Art.Nr. 152901. doi:10.1016/j.jnucmat.2021.152901

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

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

25 years QUENCH program. Main results of the QUENCH bundle tests
Stuckert, J.; Große, M.; Steinbrück, M.
2019, October 22. 25th International QUENCH Workshop (2019), Karlsruhe, Germany, October 22–24, 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, October 22. 25th International QUENCH Workshop (2019), Karlsruhe, Germany, October 22–24, 2019

Results of the bundle test QUENCH-19 with FeCrAl claddings
Stuckert, J.; Grosse, M.; Steinbrueck, M.; Terrani, K.
2019. Proceedings of Global/Top Fuel 2019, Seattle, WA, September 22-26, 2019, 922–927, American Nuclear Society (ANS)

25 years QUENCH program. Highlights of separate-effects tests
Steinbrück, M.; Stuckert, J.; Große, M.
2019, October 22. 25th International QUENCH Workshop (2019), Karlsruhe, Germany, October 22–24, 2019. doi:10.5445/IR/1000100298

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

Experimental results of the bundle test QUENCH-19 with FeCrAl claddings
Stuckert, J.; Große, M.; Steinbrück, M.; Terrani, K.
2019, May 17. ATF Topical Meeting (2019), Shenzhen, China, May 16–17, 2019

Lessons learned from the QUENCH-LOCA experiments at KIT
Stuckert, J.
2019, March 13. 23rd International Seminar ZIRAT on Zirconium Alloy Technology (2019), Palma, Spain, March 11–13, 2019

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

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

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

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

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, Germany, November 13–15, 2018

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

Update of the QUENCH program
Steinbrueck, M.; Stuckert, J.; Grosse, M.
2018. 24th International QUENCH Workshop (2018), Karlsruhe, Germany, November 13–15, 2018

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

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

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

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

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, Germany, May 29–30, 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

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

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

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

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, October 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, October 17. 23rd International QUENCH Workshop, Karlsruhe Institute of Technology, Karlsruhe, 17.-19.10.2017

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

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, July 6. CLADS workshop, July 5-6 , 2017, Tomioka, Fukushima, J

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

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, The American Society of Mechanical Engineers (ASME). doi:10.1115/ICONE24-60916

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

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, The American Society of Mechanical Engineers (ASME). doi:10.1115/ICONE24-60061

Hydride precipitation, fracture and plasticity mechanisms in pure zirconium and Zircaloy-4 at temperatures typical for the postulated loss-of-coolant accident
Pshenichnikov, A.; Stuckert, J.; Walter, M.
2016. Nuclear engineering and design, 301, 366–377. doi:10.1016/j.nucengdes.2016.03.024

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, The 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, United Kingdom, July 22–28, 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, The 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, United Kingdom, July 22–28, 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

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, Germany, October 27–29, 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

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

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, The American Society of Mechanical Engineers (ASME)

Microstructure and mechanical properties of Zircaloy-4 cladding hydrogenated at temperatures typical for loss-of-coolant accident (LOCA) conditions
Pshenichnikov, A.; Stuckert, J.; Walter, M.
2015. Nuclear engineering and design, 283, 33–39. doi:10.1016/j.nucengdes.2014.06.022

Post-test calculation of the QUENCH-17 bundle experiment with debris formation and bottom water reflood using thermal hydraulic and severe fuel damage code SOCRAT/V3
Vasiliev, A.; Stuckert, J.
2015. Nuclear engineering and design, 283, 21–32. doi:10.1016/j.nucengdes.2014.03.011

A comparison of core degradation phenomena in the CORA, QUENCH, Phebus SFD and Phebus FP experiments
Haste, T.; Steinbrück, M.; Barrachin, M.; Luze, O. de; Grosse, M.; Stuckert, J.
2015. Nuclear engineering and design, 283, 8–20. doi:10.1016/j.nucengdes.2014.06.035

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

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

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.; Luze, O. de; Grosse, M.; Stuckert, J.
2013. Proceedings of the 22nd International Conference Nuclear Energy for New Europe (NENE2013), Bled, SLO, September 9-12, 2013. Ed.: L. Cizelj, Nuclear Society of Slovenia

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.; Luze, O. de; Grosse, M.; Stuckert, J.
2013. 22nd International Conference Nuclear Energy for New Europe (NENE2013), Bled, SLO, September 9-12, 2013

Neutron imaging investigations of the hydrogen related degradation of the mechanical properties of zircaloy-4 cladding tubes
Grosse, M.; Valance, S.; Stuckert, J.; Steinbrück, M.; Walter, M.; Kaestner, A.; Hartmann, S.; Santisteban, J.
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

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 (ANS)

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 Verlags- und Verwaltungsgesellschaft mbH

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. 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

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 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 and calculation results of the integral reflood test QUENCH-15 with ZIRLOsup(T)sup(M) cladding tubes in comparison with results of previous QUENCH tests
Stuckert, J.; Birchley, J.; Große, B.; Jaeckel, B.; Steinbrück, M.
2011. Nuclear Engineering and Design, 241, 3224–3233. doi:10.1016/j.nucengdes.2011.05.004

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, Germany, November 16–18, 2010

Application of neutron radiography to study material processes during hypothetical severe accidents in nuclear reactors
Grosse, M.; Steinbrück, M.; Stuckert, J.
2010. Materials Science and Engineering (MSE 2010), Darmstadt, August 24-26, 2010

Parameters influencing the secondary hydrogenation of Zr-Sn and Zr-Nb alloys during steam oxidation under LOCA and severe accident conditions
Grosse, M. K.; Steinbrück, M.; Stuckert, J.
2010. Proc.of the 18th Internat.Conf.on Nuclear Engineering (ICONE-18), Xi’an, China, May 17-21, 2010 CD-ROM Paper ICONE18-29405 New York, N.Y. : ASME, 2010

Steam and air oxidation behavior of nuclear fuel claddings at severe accident conditions
Grosse, M.; Steinbrück, M.; Stuckert, J.
2010. Materials Research Society Spring Meeting, San Francisco, Calif., April 5-9, 2010

Quench phenomena during reflood of an overheated reactor core
Stuckert, J.; Große, M.; Steinbrück, M.
2010. 1st Internat.Conf.on Materials for Energy, Karlsruhe, July 4-8, 2010 Extended Abstracts Frankfurt a.M. : Dechema, 2010

Fuel rod cladding material behavior under severe accident conditions
Grosse, M.; Stuckert, J.; Steinbrück, M.
2010. Materials Research Society Fall Meeting, Boston, Mass., November 30 - December 4, 2009 Materials Research Society Spring Meeting, San Francisco, Calif., April 5-9, 2010

Experimental and calculation results of the integral reflood test QUENCH-14 with M5 cladding tubes
Stuckert, J.; Birchley, J.; Grosse, M.; Jaeckel, B.; Steinbrück, M.
2010. Annals of Nuclear Energy, 37, 1036–47. doi:10.1016/j.anucene.2010.04.015

Synopsis and outcome of the QUENCH experimental program
Steinbrück, M.; Große, M.; Sepold, L.; Stuckert, J.
2010. Nuclear Engineering and Design, 240, 1714–27. doi:10.1016/j.nucengdes.2010.03.021

High-temperature oxidation and quench behaviour of zircaloy-4 and E110 cladding alloys
Steinbrück, M.; Birchley, J.; Boldyrev, A. V.; Goryachev, A. V.; Grosse, M.; Haste, T. J.; Hozer, Z.; Kisselev, A. E.; Nalivaev, V. I.; Semishkin, V. P.; Sepold, L.; Stuckert, J.; Ver, N.; Veshchunov, M. S.
2010. Progress in Nuclear Energy, 52, 19–36. doi:10.1016/j.pnucene.2009.07.012

Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences
Dubourg, R.; Austregesilo, H.; Bals, C.; Barrachin, M.; Birchley, J.; Haste, T.; Lamy, J. S.; Lind, T.; Maliverney, B.; Marchetto, C.; Pinter, A.; Steinbrück, M.; Stuckert, J.; Trambauer, K.; Vimi, A.
2010. Progress in Nuclear Energy, 52, 97–108. doi:10.1016/j.pnucene.2009.09.012

Experimental and post-test calculation results of the integral reflood test QUENCH-12 with a VVER-type bundle
Stuckert, J.; Große, M.; Steinbrück, M.
2009. Computational and Experimental Studies of LWR Fuel Element Behvior under beyond Design Basis Accidents and Reflood Conditions : Internat.Scientific and Technical Meeting, Moskva, Russia, July 27-28, 2009

Lessons learned from the QUENCH programme at FZK
Steinbrück, M.; Große, M.; Sepold, L.; Stuckert, J.
2009. Steinbrück, M. [Hrsg.] Proc.of the 15th Internat.QUENCH Workshop, Karlsruhe, November 3-5, 2009 CD-ROM Karlsruhe : Karlsruhe Inst.of Technology, Campus North, 2009

Update of the QUENCH program
Steinbrück, M.; Große, M.; Sepold, L.; Stuckert, J.
2009. CSARP Meeting (CSARP = Cooperative Severe Accidents Research Programme), Bethesda, Md., September 15-18, 2009 Folien auf CD-ROM Washington, D.C. : U.S.Nuclear Regulatory Commission, 2009

Lessons learned from the QUENCH programme at FZK
Steinbrück, M.; Große, M.; Sepold, L.; Stuckert, J.
2009. NEA/SARNET2 Workshop on In-Vessel Coolability, Issy-les-Moulineaux, F, October 12-14, 2009 Proc.on CD-ROM Issy-les-Moulineaux : OECD/NEA, 2009

R&D on reflooding of degraded cores in SARNET. Focus on PEARL new IRSN facility
Stenne, N.; Fichot, F.; Dorsselaere, J. P. van; Tromm, W.; Steinbrück, M.; Stuckert, J.; Buck, M.
2009. EUROSAFE 2009, Bruxelles, B, November 2-3, 2009

Experimental results of reflood bundle test QUENCH-15 with ZIRLOsup(T)sup(M) cladding tubes
Stuckert, J.; Große, J.; Sepold, L.; Steinbrück, M.
2009. Steinbrück, M. [Hrsg.] Proc.of the 15th Internat.QUENCH Workshop, Karlsruhe, November 3-5, 2009 CD-ROM Karlsruhe : Karlsruhe Inst.of Technology, Campus North, 2009

The new Quench-LOCA tests
Sepold, L.; Große, M.; Steinbrück, M.; Stuckert, J.; Walter, M.
2009. Steinbrück, M. [Hrsg.] Proc.of the 15th Internat.QUENCH Workshop, Karlsruhe, November 3-5, 2009 CD-ROM Karlsruhe : Karlsruhe Inst.of Technology, Campus North, 2009

Influence of oxide layer morphology on hydrogen uptake of zirconium alloys during steam oxidation
Große, M.; Lehmann, E.; Steinbrück, M.; Stuckert, J.
2009. Computational and Experimental Studies of LWR Fuel Element Behavior under beyond Design Basis Accidents and Reflood Conditions : Internat.Scientific and Technical Meeting, Moskva, Russia, July 27-28, 2009

Experimental and post-test calculation results of the integral reflood test QUENCH-12 with a VVER-type bundle
Stuckert, J.; Birchley, J.; Große, M.; Haste, T.; Sepold, L.; Steinbrück, M.
2009. Annals of Nuclear Energy, 36, 183–92. doi:10.1016/j.anucene.2008.11.024

Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation
Große, M.; Lehmann, E.; Steinbrück, M.; Kühne, G.; Stuckert, J.
2009. Journal of Nuclear Materials, 385, 339–45. doi:10.1016/j.jnucmat.2008.12.021

Post-test analysis of the QUENCH-13 experiment
Birchley, J.; Austregesilo, H.; Bals, C.; Dubourg, R.; Haste, T.; Lamy, J. S.; Lind, T.; Maliverney, B.; Marchetto, C.; Pinter, A.; Steinbrück, M.; Stuckert, J.; Trambauer, K.
2008. Internat.Conf.Nuclear Energy for New Europe 2008, Portoroz, SLO, September 8-11, 2008

Comparison of the severe accident behaviour of advanced nuclear fuel rod cladding materials
Grosse, M.; Sepold, L.; Steinbrück, M.; Stuckert, J.; Ver, N.
2008. Internat.Topical Meeting on Safety of Nuclear Installations (TOPSAFE), Dubrovnik, HR, September 30 - October 3, 2008

Influence of oxide layer morphology on hydrogen concentration in Zr-Sn and Zr-Nb alloys after high temperature steam oxidation
Große, M.; Lehmann, E.; Steinbrück, M.; Kühne, G.; Stuckert, J.
2008. European Materials Research Society Spring Meeting, Strasbourg, F, May 26-30, 2008

Status of studies on high-temperature oxidation and quench behaviour of zircaloy-4 and E110 cladding alloys
Steinbrück, M.; Birchley, J.; Goryachev, A. V.; Grosse, M.; Haste, T. J.; Hozer, Z.; Kisselev, A. E.; Nalivaev, V. I.; Semishkin, V. P.; Sepold, L.; Stuckert, J.; Ver, N.; Veshchunov, M. S.
2008. 3rd European Review Meeting on Severe Accident Research (ERMSAR-2008), Nesseber, BG, September 23-25, 2008

Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences
Dubourg, R.; Austregesilo, H.; Bals, C.; Barrachin, M.; Birchley, J.; Haste, T.; Nagy, I.; Lamy, J. S.; Lind, T.; Maliverney, B.; Marchetto, C.; Pinter, A.; Steinbrück, M.; Stuckert, J.; Trambauer, K.; Vimi, A.
2008. 3rd European Review Meeting on Severe Accident Research (ERMSAR-2008), Nesseber, BG, September 23-25, 2008

Update of the QUENCH program
Steinbrück, M.; Große, M.; Sepold, L.; Stuckert, J.
2008. CSARP Meeting (CSARP = Cooperative Severe Accidents Research Programme), Bethesda, Md., September 16-18, 2008

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.
2008. International Journal of Nuclear Energy Science and Technology, (2007), 3, 287–301

Quantification of hydrogen uptake of steam-oxidized zirconium alloys by means of neutron radiography
Grosse, M.; Kühne, G.; Steinbrück, M.; Lehmann, E.; Stuckert, J.; Vontobel, P.
2008. Journal of Physics: Condensed Matter, 20, 104263/1–7. doi:10.1088/0953-8984/20/10/104263

Pre-test calculational support for the QUENCH-13 experiment
Haste, T.; Birchley, J.; Lamy, J. S.; Maliverney, B.; Austregesilo, H.; Bals, C.; Trambauer, K.; Steinbrück, M.; Stuckert, J.
2008. Proc.of the 2008 Internat.Congress on Advances in Nuclear Power Plants (ICAPP’08), Anaheim, Calif., June 8-12, 2008 CD-ROM Paper 8065 LaGrange Park, Ill. : American Nuclear Society, 2008

Results of the QUENCH-12 experiment on reflood of a VVER-type bundle
Stuckert, J.; Goryachev, A.; Große, M.; Heck, M.; Ivanova, I.; Schanz, G.; Sepold, L.; Stegmaier, U.; Steinbrück, M.
2008. FZKA. doi:10.5445/IR/270072587

FZK contribution to reactor safety research in Europe.Part 1: In-vessel core melt behavior
Tromm, W.; Miassoedov, A.; Steinbrück, M.; Stuckert, J.; Sepold, L.
2008. Internat.Workshop on Passive Safety Systems in Advanced PWRs (IPASS), Shanghai, China, April 28-30, 2008 Proc.on CD-ROM Paper I04 Shanghai : Shanghai Jiao Tong University, 2008

European research on the corium issues within the SARNET network of excellence
Journeau, C.; Bonnet, J. M.; Godin-Jacqmin, L.; Piluso, P.; Tarabelli, D.; Dufour, E.; Spindler, B.; Nicolas, L.; Altstadt, E.; Atkhen, K.; Dutheillet, Y.; Lamy, J. S.; Bandini, G.; Ederli, S.; Barrachin, M.; Cranga, M.; Duriez, C.; Fichot, F.; Repetto, G.; Koundy, V.; Birchley, J.; Bottomley, D.; Wiss, T.; Buck, M.; Burger, M.; Cheynet, B.; Dimov, D.; Grudev, P.; Stefanova, A.; Dinh, T. N.; Ma, W. M.; Sehgal, B. R.; Drath, T.; Hollands, T.; Kleinhietpass, I.; Koch, M.; Duspiva, J.; Kiselova, M.; Kujal, B.; Vokac, P.; Erdmann, W.; Müller, C.; Spengler, C.; Fischer, M.; Schmidt, W.; Hellmann, S.; Foit, J. J.; Miassoedov, A.; Steinbrück, M.; Stuckert, J.; Gallego, E.; Garcia Martin, M.; Meleg, T.; Ohai, D.; Matejovic, P.; Mathew, M.; Sdouz, G.; Sevon, T.
2008. Proc.of the 2008 Internat.Congress on Advances in Nuclear Power Plants, Anaheim, Calif., June 8-12, 2008 CD-ROM Paper 8047 LaGrange Park, Ill. : American Nuclear Society, 2008

Experimental and post-test calculation results of the integral reflood test QUENCH-12 with a VVER-type bundle
Stuckert, J.; Birchley, J.; Große, M.; Haste, T.; Sepold, L.; Steinbrück, M.
2008. Proc.of the 2008 Internat.Congress on Advances in Nuclear Power Plants (ICAPP’08), Anaheim, Calif., June 8-12, 2008 CD-ROM Paper 8116 LaGrange Park, Ill. : American Nuclear Society, 2008

Severe fuel damage experiments with advanced cladding materials to be performed in the QUENCH facility (QUENCH-ACM)
Sepold, L.; Große, M.; Steinbrück, M.; Stuckert, J.
2008. Proc.of the 16th Internat.Conf.on Nuclear Engineering (ICONE-16), Orlando, Fla., May 11-15, 2008 CD-ROM Paper ICONE16-48074 New York, N.Y. : ASME, 2008

First results of the QUENCH-13 bundle experiment with a silver-indium-cadmium control rod
Stuckert, J.; Sepold, L.; Große, M.; Stegmaier, U.; Steinbrück, M.; Birchley, J.; Haste, T.; Lind, T.; Nagy, I.; Vimi, A.
2008. SARNET 4th Annual Review Meeting, Bled, SLO, January 21-25, 2007

SARNET benchmark on QUENCH-11. Final report
Stefanova, A.; Drath, T.; Duspiva, J.; Erdmann, W.; Fichot, F.; Guillard, G.; Groudev, P.; Hering, W.; Hollands, T.; Homann, C.; Koch, M. K.; Sepold, L.; Steinbrück, M.; Stuckert, J.; Trambauer, K.; Vasilev, A.
2008. FZKA. doi:10.5445/IR/270070729

The QUENCH-ACM test series
Sepold, L.; Große, M.; Stegmaier, U.; Steinbrück, M.; Stuckert, J.
2007. Steinbrück, M. [Hrsg.] Proc.of the 13th Internat.Quench Workshop, Karlsruhe, November 20-22, 2007 CD-ROM Karlsruhe : Forschungszentrum Karlsruhe GmbH, 2007

First results of the QUENCH-13 bundle experiment with a silver-indium-cadmium control rod
Stuckert, J.; Moch, J.; Sepold, L.; Große, M.; Stegmaier, U.; Steinbock, L.; Steinbrück, M.; Lind, T.; Nagy, I.; Vimi, A.
2007. Steinbrück, M. [Hrsg.] Proc.of the 13th Internat.Quench Workshop, Karlsruhe, November 20-22, 2007 CD-ROM Karlsruhe : Forschungszentrum Karlsruhe GmbH, 2007

Status of the QUENCH program at FZK
Steinbrück, M.; Große, M.; Stegmaier, U.; Steinbock, L.; Heck, M.; Laier, J.; Moch, J.; Schanz, G.; Sepold, L.; Steiner, H.; Stuckert, J.; Hering, W.; Homann, C.; Scholtyssek, W.
2007. Steinbrück, M. [Hrsg.] Proc.of the 12th Internat.Quench Workshop, Karlsruhe,October 24-25, 2006 CD-ROM Karlsruhe : Forschungszentrum Karlsruhe GmbH, 2006

QUENCH program: recent results and future activities
Steinbrück, M.; Große, M.; Sepold, L.; Stuckert, J.
2007. Cooperative Severe Accident Research Program Meeting (CSARP), Albuquerque, N.M., September 18-19, 2007

Vergleich des Notkühlverhaltens von PWR und WWER
Stuckert, J.; Steinbrück, M.; Sepold, L.; Große, M.
2007. Vortr.: Forschungszentrum Rossendorf, Dresden, 7.Juni 2007

Determination of the hydrogen uptake of steam-oxidised zirconium alloys by means of quantitative analysis of neutron radiographs
Große, M.; Steinbrück, M.; Stuckert, J.; Lehmann, E.; Kühne, G.; Vontobel, P.
2007. European Conf.on Neutron Scattering (ECNS 2007), Lund, S, June 24-29, 2007

Severe fuel damage experiments performed in the QUENCH facility with 21-rod bundles of LWR-type
Sepold, L.; Hering, W.; Schanz, G.; Scholtyssek, W.; Steinbrück, M.; Stuckert, J.
2007. Nuclear Engineering and Design, 237, 2157–64. doi:10.1016/j.nucengdes.2007.03.020

Results of boil-off experiment QUENCH-11
Hering, W.; Groudev, P.; Heck, M.; Homann, C.; Schanz, G.; Sepold, L.; Stefanova, A.; Stegmaier, U.; Steinbrück, M.; Steiner, H.; Stuckert, J.
2007. Wissenschaftliche Berichte, FZKA-7247 (Juni 2007) SAM-LACOMERA-D18. doi:10.5445/IR/270068456

Results of the Quench-12 experiment on reflood of a VVER-type bundle
Stuckert, J.; Sepold, L.; Steinbrück, M.
2007. Jahrestagung Kerntechnik 2007, Karlsruhe, 22.-24.Mai 2007 Berlin : INFORUM GmbH, 2007 CD-ROM

Results of the QUENCH-12 reflood experiment with a VVER-type bundle
Stuckert, J.; Sepold, L.; Steinbrück, M.
2007. Proc.of the 15th Internat.Conf.on Nuclear Engineering (ICONE-15), Nagoya, J, April 22-26, 2007 CD-ROM Paper ICONE-15-10257 Tokyo : Japan Society of Mechanical Engineers, 2007

Results of the QUENCH-12 reflood experiment with a VVER-type bundle
Stuckert, J.; Sepold, L.; Große, M.; Stegmaier, U.; Steinbock, L.; Steinbrück, M.
2007. SARNET 3rd Annual Progress Meeting, Garching, January 30 - February 2, 2007

Post-test appearance of QUENCH-11 bundle
Stegmaier, U.; Stuckert, J.; Sepold, L.
2006. Steinbrück, M. [Hrsg.] Proc.of the 12th Internat.Quench Workshop, Karlsruhe,October 24-25, 2006 CD-ROM Karlsruhe : Forschungszentrum Karlsruhe GmbH, 2006

Results of the QUENCH-12 experiment on reflood of the VVER bundle
Stuckert, J.; Große, M.; Moch, J.; Sepold, L.; Stegmaier, U.; Steinbock, L.; Steinbrück, M.
2006. Steinbrück, M. [Hrsg.] Proc.of the 12th Internat.Quench Workshop, Karlsruhe,October 24-25, 2006 CD-ROM Karlsruhe : Forschungszentrum Karlsruhe GmbH, 2006

QUENCH: Experimente zum Abschrecken eines überhitzten Reaktorkerns
Steinbrück, M.; Große, M.; Stuckert, J.; Sepold, L.; Schanz, G.
2006. Treffen der Materialforscher der Forschungszentren Karlsruhe und Jülich, Karlsruhe, 19.-20.Juni 2006

Introduction of the Quench-13 experiment with AIC absorber
Sepold, L.; Steinbrück, M.; Stuckert, J.
2006. SARNET Source Term WP 14.1 Progress Meeting, Aix-en-Provence, F, October 17, 2006

Experiments on air ingress during severe accidents in LWRS
Steinbrück, M.; Miassoedov, A.; Schanz, G.; Sepold, L.; Stegmaier, U.; Stuckert, J.
2006. Nuclear Engineering and Design, 236, 1709–19. doi:10.1016/j.nucengdes.2006.04.010

Development of the metallic layer on the surface of oxidised Zry-cladding under steam starvation conditions
Stuckert, J.; Steinbrück, M.; Stegmaier, U.
2006. ISTC/WTZ Progress Meeting, Moskva, Russia, July 3-6, 2006

Review of the QUENCH-12 (QUENCH/WWER) pre-test calculations and high-temperature oxidation rate of Zr1%Nb
Stuckert, J.; Große, M.; Stegmaier, U.
2006. ISTC/WTZ Progress Meeting, Moskva, Russia, July 3-6, 2006

A QUENCH experiment including an air ingress phase prior to flooding
Sepold, L.; Hozer, Z.; Schanz, G.; Stegmaier, U.; Steinbrück, M.; Stuckert, J.
2006. American Nuclear Society Annual Meeting, Reno, Nev., June 4-8, 2006

A QUENCH experiment including an air ingress phase prior to flooding
Sepold, L.; Hozer, Z.; Schanz, G.; Stegmaier, U.; Steinbrück, M.; Stuckert, J.
2006. Transactions of the American Nuclear Society, Auch auf CD-ROM, 94, 140–41

Results of the QUENCH-10 experiment on air ingress
Schanz, G.; Heck, M.; Hozer, Z.; Matus, L.; Nagy, I.; Sepold, L.; Stegmaier, U.; Steinbrück, M.; Steiner, H.; Stuckert, J.; Windberg, P.
2006. Wissenschaftliche Berichte, FZKA-7087 (Mai 2006) SAM-LACOMERA-D09. doi:10.5445/IR/270064700

Synthesis of the QUENCH program and its impact on code modeling
Steinbrück, M.; Hering, W.; Stuckert, J.; Birchley, J.; Brunet-Thibault, E.; Drath, T.; Seiler, N.; Trambauer, K.; Veschunov, M. S.
2005. 1st European Review Meeting on Severe Accident Research (ERMSAR-2005), Aix-en- Provence, F, November 14-16, 2005

Status of the QUENCH-11 test preparations: first pre-test results
Stuckert, J.; Hering, W.; Homann, C.; Moch, J.; Sepold, L.; Stegmaier, U.; Steinbrück, M.
2005. Steinbrück, M. [Hrsg.] Proc.of the 11th Internat.QUENCH Workshop, Karlsruhe, October 25-27, 2005 CD-ROM Karlsruhe : Forschungszentrum Karlsruhe GmbH

Status of the QUENCH program at FZK
Große, M.; Stegmaier, U.; Steinbock, L.; Steinbrück, M.; Heck, M.; Laier, J.; Moch, J.; Schanz, G.; Sepold, L.; Steiner, H.; Stuckert, J.; Hering, W.; Homann, C.; Miassoedov, A.; Scholtyssek, W.
2005. Steinbrück, M. [Hrsg.] Proc.of the 11th Internat.QUENCH Workshop, Karlsruhe, October 25-27, 2005 CD-ROM Karlsruhe : Forschungszentrum Karlsruhe GmbH

Experimental and computational results of the QUENCH-08 experiment. (Reference to QUENCH-07)
Stuckert, J.; Boldyrev, A. V.; Miassoedov, A.; Palagin, A. V.; Schanz, G.; Sepold, L.; Shestak, V. E.; Stegmaier, U.; Steinbock, L.; Steinbrück, M.; Steiner, H.; Veshchunov, M. S.
2005. Wissenschaftliche Berichte, FZKA-6970 (August 2005). doi:10.5445/IR/270062382

Degradation of the cladding oxide layer under steam starvation conditions
Stuckert, J.; Stegmaier, U.
2002. 8th Internat.Quench Workshop, Karlsruhe, October 29-31, 2002

Experiments on air ingress during severe accidents
Steinbrück, M.; Miassoedov, A.; Schanz, G.; Sepold, L.; Stegmaier, U.; Stuckert, J.
2005. Proc.of the 13th Internat.Conf.on Nuclear Engineering (ICONE-13), Beijing, China, May 16-20, 2005 CD-ROM Paper 50080 Beijing : Chinese Nuclear Society, 2005

Modelling of B₄C oxidation by steam at high temperatures based on separate-effects tests and its application to the bundle experiment QUENCH-07
Veshchunov, M. S.; Berdyshev, A. V.; Boldyrev, A. V.; Palagin, A. V.; Shestak, V. E.; Steinbrück, M.; Stuckert, J.
2005. Wissenschaftliche Berichte, FZKA-7118 (Juni 2005). doi:10.5445/IR/270061854

Core loss during a severe accident (COLOSS)
Adroguer, B.; Dorsselaere, J. P. van; Chatelard, P.; Cocuaud, N.; Bertrand, F.; Bellenfant, L.; Bottomley, D.; Knoche, D.; Vrtilkova, V.; Müller, K.; Schanz, G.; Miassoedov, A.; Steinbrück, M.; Stuckert, J.; Krauss, W.; Hering, W.; Homann, C.; Hozer, Z.; Bandini, G.; Birchley, J.; Kleinhietpass, I.; Buck, M.; Benitez, F.; Virtanen, E.; Marguet, S.; Azarian, G.; Plank, H.; Berdyshev, A.; Veshchunov, M.; Kobzar, V.; Zvonarev, Y.; Goryachev, A.
2005. FISA-2003 : EU Research in Reactor Safety ; Conclusion Symp.on Shared-Cost and Concerted Actions, Luxembourg, L, November 10-13, 2003 Luxembourg : Office for Official Publications of the European Communities, 2004 S.342-47 EUR-21026 Auch auf CD-ROM (Preproc. S.328-34)