|
Autor |
Titel | Zeitsschrift |
| L. Sepold, P. Hofmann, W. Leiling, A. Miassoedov, D. Piel, L. Schmidt, M. Steinbrück |
Reflooding experiments with LWR-type fuel rod simulators in the QUENCH facility |
Nuclear Engineering and Design, 204 (2001) 205–220 |
| B. Adroguer, P. Chatelard, J.P. Van Dorsselaere, C. Duriez, N. Cocuaud, L. Bellenfant, D. Bottomley, V. Vrtilkova, K. Mueller, W. Hering, C. Homann, W. Krauss, A. Miassoedov, M. Steinbrück, J. Stuckert, Z. Hozer, G.Bandini, J. Birchley, T.v. Berlepsch, M. Buck, J.A.F. Benitez , E. Virtanenm, S. Marguet, G. Azarian, H. Plank, M. Veshchunov, Y. Zvonarev, A. Goryachev |
Core loss during a severe accident (COLOSS) | Nuclear Engineering and Design, 221 (2003) 55–76 |
| G. Schanz, B. Adroguer, A. Volchek | Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations Part I. Experimental database and basic modeling |
Nuclear Engineering and Design, 232 (2004) 75–84 |
| H. Steiner | Modeling of boron carbide oxidation in steam | Journal of Nuclear Materials 345 (2005) 75–83 |
| B. Adroguer, P. Chatelard, J.P. Van Dorsselaere, C. Duriez, N. Cocuaud, L. Bellenfant, D. Bottomley, V. Vrtilkova, K. Mueller, W. Hering, C. Homann, W. Krauss, A. Miassoedov, M. Steinbrück, J. Stuckert, Z. Hozer, G.Bandini, J. Birchley, T.v. Berlepsch, M. Buck, J.A.F. Benitez , E. Virtanenm, S. Marguet, G. Azarian, H. Plank, M. Veshchunov, Y. Zvonarev, A. Goryachev |
Core loss during a severe accident (COLOSS) | Nuclear Engineering and Design 235 (2005) 173–198 |
| Martin Steinbrück,∗, Alexei Miassoedov, Gerhard Schanz, Leo Sepold, Ulrike Stegmaier, Juri Stuckert |
Experiments on air ingress during severe accidents in LWRS | Nuclear Engineering and Design 236 (2006) 1709–1719 |
| L. Sepold, W. Hering, G. Schanz, W. Scholtyssek, M. Steinbrück, J. Stuckert | Severe fuel damage experiments performed in the QUENCH facility with 21-rod bundles of LWR-type |
Nuclear Engineering and Design 237 (2007) 2157–2164 |
| M Grosse, G Kuehne, M Steinbrueck, E Lehmann, J Stuckert and P Vontobe |
Quantification of hydrogen uptake of steam-oxidized zirconium alloys by means of neutron radiography |
J. Phys.: Condens. Matter 20 (2008) 104263 (7pp) |
| Mirco Große, Eberhard Lehmann, Martin Steinbrück, Guido Kühne, Juri Stuckert | Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation |
Journal of Nuclear Materials 385 (2009) 339–345 |
| L. Sepold, T. Lind, A. Pintér Csordás, U. Stegmaier, M. Steinbrück, J. Stuckert | AgInCd control rod failure in the QUENCH-13 bundle test | Annals of Nuclear Energy 36 (2009) 1349–1359 |
| J. Stuckert, J. Birchley, M. Große, T. Haste, L. Sepold, M. Steinbrück | Experimental and post-test calculation results of the integral reflood test QUENCH-12 with a VVER-type bundle |
Annals of Nuclear Energy 36 (2009) 183–192 |
| R. Dubourg, H. Austregesilo, C. Bals, M. Barrachin, J. Birchley, T. Haste, J.S. Lamy, T. Lind, B. Maliverney, C. Marchetto, A. Pinter, M. Steinbrück, J. Stuckert, K. Trambauer, A. Vimi |
Understanding the behaviour of absorber elements in silver–indium–cadmium control rods during PWR severe accident sequences |
Progress in Nuclear Energy 52 (2010) 97–108 |
| Terttaliisa Lind, Anna Pintér Csordás, Imre Nagy, Juri Stuckert | Aerosol behavior during SIC control rod failure in QUENCH-13 test | Journal of Nuclear Materials 397 (2010) 92–100 |
| M. Steinbrück M. Große, L. Sepold, J. Stuckert | Synopsis and outcome of the QUENCH experimental program | Nuclear Engineering and Design 240 (2010) 1714–1727 |
| M. Steinbrück, J. Birchley, A.V. Boldyrev, A.V. Goryachev, M. Grosse, T.J. Haste, Z. Hózer, A.E. Kisselev, V.I. Nalivaev, V.P. Semishkin, L. Sepold, J. Stuckert, N. Vér, M.S. Veshchunov |
High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys |
Progress in Nuclear Energy 52 (2010) 19–36 |
| J. Stuckert, J. Birchley, M. Grosse, B. Jaeckel, M. Steinbrück | Experimental and calculation results of the integral reflood test QUENCH-14 with M5 cladding tubes |
Annals of Nuclear Energy 37 (2010) 1036–1047 |
| J. Birchley and J. Stuckert | Analysis of QUENCH-ACM Experiments Using SCDAP/RELAP5 | Journal of Energy and Power Engineering 5 (2011) 918-927 |
| J. Stuckert, J. Birchley, M. Große, B. Jaeckel, M. Steinbrück | Experimental and calculation results of the integral reflood test QUENCH15 with ZIRLOTM cladding tubes in comparison with results of previous QUENCH tests |
Nuclear Engineering and Design 241 (2011) 3224– 3233 |
| D. Bottomley, J. Stuckert, P. Hofmann, L. Tocheny, M. Hugon, C. Journeau, B. Clément, S. Weber, S. Guentay, Z. Hozer, L. Herranz, A. Schumm, F. Oriolo, E. Altstadt, M. Krause, M. Fischer, V.B. Khabensky, S.V. Bechta,1, M.S. Veshchunov, A.V. Palagin, A.E. Kiselev, V.I. Nalivaev, A.V. Goryachev, V. Zhdanov, V. Baklanov |
Severe accident research in the core degradation area: An example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center |
Nuclear Engineering and Design 252 (2012) 226– 241 |
| M. Große, M. Steinbrück, J. Stuckert, A. Kastner, B. Schillinger |
Application of neutron radiography to study material processes during hypothetical severe accidents in nuclear reactors |
J Mater Sci (2012) 47:6505–6512 DOI 10.1007/s10853-011-5553-1 |
| M. Grosse, J. Stuckert, M. Steinbrück, A. Kaestner | Secondary hydriding during LOCA – Results from the QUENCH-L0 test | Journal of Nuclear Materials 420 (2012) 575–582 |
| M. Grosse, J. Stuckert, M.Steinbrück, A. Kaestner, S. Hartmann | Neutron radiography and tomography investigations of the secondary hydriding of zircaloy-4 during simulated loss of coolant nuclear accidents |
Physics Procedia 43 ( 2013 ) 294 – 306 |
| J. Stuckert, M. Große, C. Rössger, M. Klimenkov, M. Steinbrück, M. Walter | QUENCH-LOCA program at KIT on secondary hydriding and results of the commissioning bundle test QUENCH-L0 |
Nuclear Engineering and Design 255 (2013) 185– 201 |
| A.D. Vasiliev, J. Stuckert | Application of thermal hydraulic and severe accident code SOCRAT/V3 to bottom water reflood experiment QUENCH-LOCA-0 |
Nuclear Engineering and Design 261 (2013) 352– 361 |
| J. Stuckert, M. Steinbrück | Experimental results of the QUENCH-16 bundle test on air ingress | Progress in Nuclear Energy 71 (2014) 134-141 |
| Leticia Fernandez-Moguel, Christine Bals, Emilie Beuzet, Christian Bratfisch, Olivia Coindreau, Zoltan Hózer, Juri Stuckert, Alexander Vasiliev, Petya Vryashkova |
SARNET2 benchmark on air ingress experiments QUENCH-10, -16 | Annals of Nuclear Energy 74 (2014) 12–23 |
| A. Vasiliev, J. Stuckert | 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 | Nuclear Engineering and Design 283 (2015) 21-32 |
| A. Pshenichnikov, J. Stuckert, M. Walter | Microstructure and mechanical properties of Zircaloy-4 cladding hydrogenated at temperatures typical for loss-of-coolant accident (LOCA) conditions. | Nuclear Engineering and Design 283 (2015) 33-39 |
| T. Haste, M. Steinbrück, M. Barrachin, O. de Luze, M. Grosse, J. Stuckert |
A comparison of core degradation phenomena in the CORA, QUENCH, Phébus FP experiments | Nuclear Engineering and Design 283 (2015) 8-20 |
| M. Grosse, J. Stuckert, C. Roessger, M. Steinbrück, M. Walter, A. Kästner | Analysis of the secondary cladding hydrogenation during the quench-LOCA bundle tests with Zircaloy-4 claddings and its influence on the cladding embrittlement |
ASTM Special Technical Publication Materials of 17th International Symposium on Zirconium in the Nuclear Industry |
| M. Grosse, C. Roessger, J. Stuckert, M. Steinbrück, A. Kästner, N. Kardjilov, B. Schillinger | Neutron Imaging Investigations of the Secondary Hydriding of Nuclear Fuel Cladding Alloys during Loss of Coolant Accidents. |
Physics Procedia 69 ( 2015) 436 – 444 Materials of 10th World Conference on Neutron Radiography 5-10 October 2014 |
|
Jäckel, B.; Bevilacqua, A.; Ducros, G.; Gauntt, R.; |
Land contamination activity data interpretation from Fukushima Daiichi accident. |
Nuclear Engineering and Design, pages 28-33 |
|
A.Pshenichnikov; J. Stuckert; M. Walter |
Hydride precipitation, fracture and plasticity mechanisms in pure zirconium and Zircaloy-4 at temperatures typical for the postulated loss-of-coolant accident. |
Nuclear Engineering and Design, pages 366-377 |
| J.Stuckert; Z. Hózer; A. Kiselev; M. Steinbrück | Cladding oxidation during air ingress. Part I: Experiments on air ingress. | Annals of Nuclear Energy Volume 93, July 2016, Pages 4-17 |
| A. Vasiliev; J. Stuckert | Application of Thermal Hydraulic and Severe Accident Code SOCRAT/V3 to Bottom Water Reflood Experiment QUENCH-LOCA-1. | Transactions of the ASME: Journal of Nuclear Engineering and Radiation Science, April 2016, vol. 2, Pages 021024-1...021024-7 |
| I. Gómez-García-Torano; V. Sánchez-Espinoza; R. Stieglitz; J. Stuckert; L. Baborde, S. Belon | Validation of ASTECV2.1 based on the QUENCH-08 experiment. | Nuclear Engineering and Design, Volume 314 (2017) Pages 29-43 |
| S. Bechta, W. Ma, A. Miassoedov, Ch. Journeau, K. Okamoto, D. Manara, D. Bottomley, M. Kurata, B. R. Sehgal, J. Stuckert, M. Steinbrueck, B. Fluhrer, T. Keim, M. Fischer, G. Langrock, P. Piluso, Z. Hozer, M. Kiselova, F. Belloni, M. Schyns | On the EU-Japan roadmap for experimental research on corium behavior. | Annals of Nuclear Energy, 124 (2019), 541-547 |
|
J. Stuckert, H. Austregesilo, Ch. Bals, Th. Hollands, A. Kiselev, D. Tomashchik, T. Yudina |
Post-test analyses of the CORA-15 bundle test with the system codes ATHLET-CD and SOCRAT | Nuclear Engineering and Design, Volume 342 (2019) Pages 320-335 |
| J. Bichley, J. Stuckert, M. Steinbrueck, M. Grosse | Preliminary interpretative analysis of the QUENCH-18 bundle test using SCDAPSim/mod3.5 | Annals of Nuclear energiy 130 (2019, pp. 20-33 |
| Kalilainen, T. Lind, J. Stuckert, T. Bergfeldt, O. Sippula, J. Jokiniemi | The measurement of Ag/in/Cd release under eir ingress conditions in the QUENCH-18 bundle test. |
Jornal of Nuclear Materials, Volume 517 (2019), Pages 315-327 |
