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Participants 2013

Family Name First Name Institution Country Presentation Title
Abolhassani Sousan PSI Switzerland  
Allison Chris Innovative Systems Software USA  
Almiashev Viacheslav A.P. Aleksandrov Research Institute of Technology (NITI) Russia Influence of oxygen potential of corium melt on corrosion of LWR vessel steel
Badelles Bellver Josep RWE Power AG  Germany  
Baklanov Viktor Institute of Atomic Energy NNC RK (IAE NNC RK) Kazakhstan Study of the processes of corium-melt retention in the reactor pressure vessel (draft)
Baláž Jozef VUJE a.s. Trnava Slovakia Assessment of the VVER440 core quenching on enhanced Mochovce 1&2 design
Bals Christine GRS Garching Germany Analytical support to experiment QUENCH-17 and first post-test calculations with ATHLET-CD
Bazyuk Sergey FSUE "SRI SIA "LUCH" Russia Development of generalizing correlation on the quench front velocity for model fuel assemblies under LOCA accident simulation
Belousov Anton KIT Germany  
Benesova Barbora CTU in Prague - Faculty of Mechanical Engineering Czech Republic  
Berkhan Ana Universität Stuttgart Germany  
Besenböck Wolfgang TÜV SÜD Industrie Service GmbH Germany  
Beuzet Emilie EDF R&D France  
Birchley Jonathan Paul Sherrer Institute Switzerland Status of PSI Air Oxidation Modelling
Boldyrev Andrey IBRAE Russia  
Bottomley David ITU Karlsruhe Germany  
Boulley Sylvain AREVA France  
Brachet Jean-Christophe CEA France Enhanced Accident Tolerant Coated Cladding
Bratfisch Christian Ruhr-Universität Bochum (RUB) Germany ATHLET-CD post-test calculation of QUENCH-17
Coindreau Olivia IRSN France Presentation of a tool developed at IRSN to quickly estimate hydrogen production during quenching.
Corson James U.S. Nuclear Regulatory Commission USA  
D'Alessandro Christophe Universität Stuttgart Germany  
Di Marcello Valentino KIT Germany Analysis of the CORA-17 bundle experiment with the ATHLET-CD code
Distler Ingrid AREVA GmbH Germany  
Ehlkes Lars EnBW Kernkraft GmbH Germany  
Fargette Andre AREVA France  
Fedotov Petr JSC A.A. Bochvar High Techn. Res. Inst. of Inorganic Materials Russia  
Fernandez-Moguel Leticia Paul Scherrer Institute Switzerland  
Gabrielli Fabrizio KIT Germany  
Gómez Ignacio KIT Germany  
Gremme Florian Ruhr-Universität Bochum Germany  
Grohé Willi TÜV SÜD Energietechnik GmbH BW Germany  
Grosse Mirco KIT Germany 1. Modelling of the hydrogen distribution in cladding tubes after LOCA 2. Neutron and X-ray imaging investigations concerning the QUENCH program
Gyori Csaba NucleoCon llc Slovak Republic  
Hagen Siegfried Formerly KIT Germany  
Haurais Florian EDF R&D France  
Hofmann Peter Formerly KIT Germany  
Hollands Thorsten GRS Germany OECD/NEA SFP Phase II Benchmark Exercise
Holt Lars Helmholtz-Zentrum Dresden-Rossendorf Germany  
Ignatyev Dmitry NPO LUCH Russia Thermomechanical and Corrosion Behavior of Pre-Hydrided E110 Sponge Based Fuel Rod Claddings. Methodology and Test Program
Imke Uwe KIT Germany  
In Wang-Kee Korea Atomic Energy Research Institute Republic of Korea Pool Boiling Critical Heat Flux and Quenching Experiments using Oxidized Zircaloy Surface
Inozemtsev Victor IAEA Austria IAEA projects on fuel modelling: invitation for collaboration
Jančovič Juraj VUJE a.s. Trnava Slovakia  
Kawahara Keisuke Innovative Systems Software USA A new B4C control rod model in RELAP/SCDAPSIM/MOD3.5
Kitagaki Toru Japan Atomic Energy Agency Japan Comparison and assumption of fuel debris properties between TMI-2 and 1F for future defueling work
Konys Juergen KIT Germany  
Kulenovic Rudi Universität Stuttgart Germany  
Laier Jutta KIT Germany  
Lecomte Marylène AREVA NP SAS France  
Leininger Simon Universität Stuttgart Germany  
Lombard Virginie EDF R&D France  
Madokoro Hiroshi The University of Tokyo Japan SCDAP model improvement with QUENCH-06 analysis
Mandapaka Kiran Kumar Bhabha Atomic Research Centre India High temperature and pressure oxidation and hydrogen pick-up behavior of Zr alloys – Effect of material and environmental factors
Miwa Shuhei Japan Atomic Energy Agency Japan Research Programs for the Accident Progression Analysis of Fukushima-Daiichi NPP at JAEA
Moch Jürgen KIT Germany  
Mokrushin Andrei NPO LUCH Russia Single Rod with Cladding of E110 Alloy Behavior in Non-LOCA Conditions
Muscher Heinrich KIT Germany Description of the TMI-2 Accident: OECD-Benchmark final results with ASTEC (SBO, LOCA)
Park Sanggil Paul Scherrer Institute Switzerland Preliminary findings on the role of nitrogen during air oxidation
Parshin Nikolay FSUE "SRI SIA "LUCH" Russia Evaluation of reflooding main characteristics for model fuel assemblies of different large-scale test facilities
Paul Blair Westinghouse Electric Sweden AB Sweden  
Pistner Christoph Oeko-Institut e.V. Germany  
Pshenichnikov Anton KIT Germany Microstructure and mechanical properties of Zircaloy-4 claddings hydrogenated at temperatures typical for LOCA conditions
Roessger Conrado KIT Germany  
Sartowska Bozena Institute of Nuclear Chemistry and Technology Poland Technologies supporting development of safe nuclear power engineering - the strategic research project in Poland
Schäfer Wolfgang EnBW Kernkraft GmbH Germany  
Schmidt Cornelia EnBW Kernkraft GmbH Germany  
Sepold Leo Formerly KIT Germany  
Sheindlin Mikhail Joint Institute for High Temperatures Russia  
Shestak Valeriy IBRAE RAN Russia  
Skarohlid Jan Czech Technical University Czech Rep. Polycrystalline diamond films as protection of zircaloy fuel cladding
Sonnenburg Heinz-Günther GRS Germany Relation between the newly derived ECR criterion and the QUENCH LOCA test results
Starosta Wojciech Institute of Nuclear Chemistry and Technology Poland Modification of the zirconium alloys surface layer with yttrium by ion implantation and plasma pulse techniques
Stefanova Antoaneta INRNE-BAS Bulgaria  
Stegmaier Ulrike KIT Germany  
Steinbock Lothar private germany  
Steinbrück Martin KIT Germany 1) Overview of QUENCH program 2) Zry-4 oxidation in mixed oxygen-nitrogen atmospheres
Stuckert Juri KIT Germany 1) Overview of LOCA tests performed at KIT during last 30 years; 2) First results of the QUENCH-LOCA-2 bundle test performed with M5® claddings; 3) Results of the QUENCH-DEBRIS bundle test.
Takanori Hoshino Japan Atomic Energy Agency Japan  
Trometer Ailine Universität Stuttgart Germany  
Van Uffelen Paul European Commission, Joint Research Centre, Institute for Transuranium Elements Germany A critical analysis of the large strain analysis in the TRANSURANUS fuel performance code for LOCA simulations
Veshchunov Mikhail IBRAE Russia Further development of the SVECHA model for Zry cladding secondary hydriding and verification against KIT and ANL tests under LOCA conditions.
Vimi András Hungarian Academy of Sciences Centre for Energy Research Hungary Secondary hydridization of fuel rod samples
Vryashkova Petya Institute for Nuclear Research and Nuclear Energy (INRNE) Bulgaria Sensitive study with Quench-16 test
Washiya Tadahiro Japan Atomic Energy Agency Japan  
Wensauer Andreas E.ON Kernkraft GmbH Germany  
Zhdanov Vladimir IBRAE Russia Study of the processes of corium-melt retention in the reactor pressure vessel