| 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 |
