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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. Buckk, 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. Buckk, 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
Volume STP 1543 (2015) 1054-1073

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.; 
Stuckert, J.

Land contamination activity data interpretation from Fukushima Daiichi accident.

Nuclear Engineering and Design,
volume 300, 15 April 2016,

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,
volume 301, May 2016,

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