Program
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Monday |
Opening of the Symposium |
0.1 |
Welcome address, Marta Žiaková, Slovak Regulatory Authority |
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0.2 |
Welcome address, Vladimír Nečas, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology |
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0.3 |
Welcome address, Vladimír Slugeň, Slovak Nuclear Society |
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0.4 |
Welcome address, Peter Líška, VUJE, Inc. |
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0.5 |
Present Status of the Project „Modernization of NPP V2 Bohunice“, Pavol Ševera, VUJE, Inc. |
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0.6 |
Safety Issues to be Solved in Mochovce NPP Units 3&4 Design Revision, Ivan Čillík, Štefan Rohár, VUJE, Inc. |
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Cofee break |
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Topic 1: |
Information about AER WG A On Improvement, Extension and Validation of Parametrized Few-Group Libraries for VVER 440 and VVER 1000, P. Mikoláš, ŠKODA JS a.s., Czech Republic |
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Inclusion of Historical Dependences of Fuel Burn-up into MOBY-DICK Code, V. Krýsl, P. Mikoláš, ŠKODA JS a.s., Czech Republic |
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12:30 - 13:30 Lunch |
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Topic 1: |
Quantitative and Quality Test of Cross Section Library ENDF/B-b2, R. Zajac, VUJE, Inc., Slovakia |
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BIPR7 Library Preparation by HELIOS, P. Dařílek, VUJE, Inc., Slovakia |
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Calculation of Isotope Burn-up and Change in Efficiency of Absorbing Elements of VVER-1000 Control and Protection System during Burn-up, O.A. Timofeeva, K.Yu. Kurakin, FSUE OKB „GIDROPRESS“, Russia |
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Cofee break |
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Topic 2: |
Determination of Reactor Parameters During Start Up Test at the TIANWAN NPP, Unit 1,S. Astakhov, A. Kravchenko, Yu. Kraynov, A.Nasedkin, S. Tsyganov, RRC “Kurchatov Institute”, Russia |
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Code Package SAPPHIRE _95&RC_ VVER. Verification on Operational Data of VVER-440 Units, Yu. A. Ananiev, K. Yu. Kurakin, FSUE OKB “GIDROPRESS”, Russia, V.G. Artyomov, FSUE NITI, Russia |
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The Power's Maneuvering Regime Simulation on 2nd Unit of Khmelnitsky HNPP, Y. Ovdiyenko, V. Khalimonchuk, A. Kuchin, State Scientific and Technical Centre on Nuclear and Radiation Safety, Ukraine |
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Tests in “Kurchatov Institute” on Research of Coolant Mixing in Fuel Exit Channel of VVER-440 Reactor, L. Kobzar, D. Oleksuk, RRC “Kurchatov Institute”, Russia |
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On the Method of Moving of Incomplete Coolant Mixing Correction in the Top Nozle of VVER-440 Assembly. Correction of Power Assemblies Using Thermocouples Readings, A. Brik, D. Oleksiuk, RRC “Kurchatov Institute”, Russia |
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Power Release Estimation Inside of Fuel Pins Neighbouring Fuel Pin with Gadolinium in a WWER-1000 Type Core, J. Mikus, NRI Řez plc, Czech Republic |
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18:30 Dinner |
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Tuesday |
Topic 3: |
AER Working Group “B” Activities in 2006, P. Dařílek, VUJE, Inc., Slovakia |
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3.2 |
Comparison of Optimizing Loading Patterns on the Basis of SA and PMA Algorithms, B. Beliczai, Paks NPP Ltd, Hungary |
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Gd-2 Fuel Cycle Benchmark - Final Definition, J. Bajgl, CEZ Inc., Dukovany NPP, Czech Republic |
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3.4 |
Utilisation of Gd-2 Fuel Assemblies at NPP Bohunice Unit 3 and 4, M. Kačmar et al, Bohunice NPP, Slovakia |
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Preliminary Comparison of Theoretical and Real Data of Cycles with Gd-II FA, P. Urban, NPP Mochovce, Slovakia |
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Cofee break |
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Topic 3: |
Four Years Re-Use of Low Burned Fuel Assemblies from Units 1&2 in Core Loadings of Units 3&4 WWER-440 at Kozloduy NPP, I. Stoyanova, A. Antov, V. Spasova, Kozloduy NPP Plc., Bulgaria |
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Results of Research and Optimization for the Third-Generation Fuel Assemblies PK-3 VVER-440, A. Gagarinsky, A. Lazarenko, M. Lizorkin, B. Saprykin, RRC “Kurchatov Institute”, Russia |
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3.8 |
236U Compensation in Recycled Uranium Fuel for the VVER Reactors, V.Yu. Plyashkevich, V.N. Proselkov, RRC “Kurchatov Institute”, Russia |
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Stationary TVSA Fuel Cycles at Kozloduy NPP WWER-1000 Reactors, K. Kamenov, Kozloduy NPP Plc., Bulgaria |
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12:30 - 13:30 Lunch |
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Topic 4: |
AER Working Group C Activity in 2006, I. Nemes, Paks NPP Ltd., Hungary |
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Modernization of In-Core Instrumentation System (ICIS) on Reactor VVER-1000, V. Mitin, RRC “Kurchatov Institute”, Russia |
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SPND Detectors Response at the Control Rod Drop in VVER-1000. Measurement and Modeling Results, V. Mitin, N. Milto, M. Kuzmichev, L. Shishkov, S. Tsyganov, RRC “Kurchatov Institute”, Russia |
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Application of New Methodology of Form-Functions Calculations in SCORPIO-VVER System, J. Šůstek, ŠKODA JS a.s., Czech Republic |
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An Advanced Tool of Nuclear Reactor Core Analysis for Reactor Physicist: VERONA-Expert System, I. Pós, Z. Kálay, G. Farkas, Paks NPP Ltd., Hungary |
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Cofee break |
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15:45 Sight-seeing tour |
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19:30 Dinner |
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Wednesday |
Topic 4: |
A new Type of In-Core Sensor Validation Outline, Š. Figedy, VUJE, Inc., Slovakia |
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Modelling of the WWER-440 Reactor for Determination of the Spatial Weight Function of Ex-Core Detectors Using MCNP-4C2 Code, G. Farkaš, SUT, Faculty of Electrical Engineering and Information Technology, Department of nuclear physics and technology, Slovakia |
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The Evaluation of Control Assembly Withdrawal by Dynamic Method - Practice Utilization, C. Strmensky, M. Minarcin, V. Petenyi, VUJE, Inc., Slovakia |
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Measurement and Evaluation Systems for NPP Commissioning, M. Eľko, VUJE, Inc., Slovakia |
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Influence of Sampling Interval Inaccuracy on Calculated Reactivity Error, M. Sedlacek, M. Elko, M. Benian, VUJE, Inc., Slovakia |
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Cofee break |
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Topic 5: |
"AER Working Group D on VVER Safety Analysis", Report of the meeting in Pisa, Italy, 26-27 April 2006, P. Siltanen, Fortum Nuclear Services Ltd, Finland |
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Results of Modeling Benchmark Problem V1000CT2 for Exercise 1 of the Phase 2 with the System Code ATHLET-BIPR8KN, S. Nikonov, , M. Lizorkin, A. Kotsarev, RRC “Kurchatov Institute”, Russia, K. Velkov, S. Langenbuch, GRS mbH, Germany |
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State of the Art Regarding the Safety Analysis of Boron Dilution Events in Germany, S. Kliem, U. Rohde, Forschungszentrum Rossendorf, Germany |
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Uncertainty Analysis for Hot Channel, I. Panka, A. Keresztúri, KFKI Atomic Energy Research Institute, Hungary |
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12:30 - 13:30 Lunch |
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Topic 5: |
Evaluation of Fuel Rod Cladding Failure, B. Hatala, VUJE, Inc., Slovakia |
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Assessment of the Thermo-Mechanical Behavior of Fuel Pins During Power's Maneuvering Regime on 2nd Unit of KHNPP", M. Ieremenko, Y.Ovdiyenko, V.Khalimonchuk, Scientific and Technical Centre on Nuclear and Radiation Safety, Ukraine |
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Cofee break |
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Topic 5: |
Detailed Analysis of Coolant Flow in VVER-440 Fuel Rod Bundle, S. Tóth, A. Aszódi, Institute of Nuclear Techniques, Budapest University of Technology and Economics, Institute of Nuclear Techniques, Hungary |
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CFD Analysis of Coolant Mixing in VVER-1000 Pressure Vessel, B. Yamaji, A. Aszódi, Budapest University of Technology and Economics, Institute of Nuclear Techniques, Hungary |
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The CFD Modeling of Coolant Flow in Fuel Assembly - Current Results and Their Application, K. Klučárová, J. Remiš, VUJE, Inc., Slovakia |
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Spectral Element Code Development for Incompressible Flow Simulations In the Subchannel of a Fuel Rod Bundle, P. Kávrán, KFKI Atomic Energy Research Institute, Hungary |
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Comparative Analysis of Exercise 2 Results of the OECD VVER-1000 MSLB benchmark, N.Kolev, E.Royer, B. Ivanov, K. Ivanov and N.Petrov, INRNE - Bulgaria, CEA Saclay - France, PSU - USA (paper only) |
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Cofee break |
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Topic 6: |
Summary of Working Group „E“, V. Chrapčiak, VUJE, Inc., Slovakia |
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The Analyses of Measured Nuclide Concentration in Project ISTC 2670, V. Chrapčiak, VUJE, Inc., Slovakia |
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6.3 |
Composition Calculations by the KARATE Code System for the Spent-Fuel Samples from the Novovoronezh Reactor, G. Hordósy, KFKI Atomic Energy Research Institute, Hungary |
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Validation of SCALE Depletion Calculations Against VVER Experimental Data, M. Manolova, N. Mihaylov, M. Peeva, INRNE, Bulgaria (paper only) |
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Calculation of Isotope Composition of WWER- 440 Spent Fuel Assembly by the NESSEL-NUKO Code System on the Basis of the ISTS Burn-Up Credit Project Data, R. Prodanova, INRNE, Bulgaria (paper only) |
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Methodology for Burnup Credit Application for VVER-440 Reactors in Slovakia, V. Chrapčiak, VUJE, Inc., Slovakia |
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18:30 Dinner |
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Thursday |
Topic 6: |
Bounding Approach in BUC Implementation in Pool at VVER 440, F. Havlůj, NRI Řež plc, Czech Republic |
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Nuclear Safety Analysis for Transport Cask TK-6 (for VVER-440) and Cover for Fresh Assemblies (for VVER-1000) in Implementation of new Fuel Types at Ukrainian NPP, Y. Bilodid, State Scientific and Technical Centre on Nuclear and Radiation Safety, Ukraine |
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Leak Testing of WWER-440 Fuel Assemblies in Slovak Wet Interim Spent Fuel Storage Facility, M. Mikloš, V. Kršjak, V. Slugeň, SUT, Faculty of Electrical Engineering and Information Technology, Department of nuclear physics and technology, Slovakia |
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Cofee break |
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Topic 7: |
Information about Activities AER Working Group “F” – Spent Fuel Transmutations, V. Lelek, NRI Řež plc., Czech Republic |
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Sustainable Fuel Cycle Alternatives for Slovakia - Evaluation Methods, P. Dařílek, VUJE, Inc., Slovakia |
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PWR and VVER Thorium Cycle Calculation, J. Breza, VUJE, Inc., Slovakia |
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Fuel Research in Halden, J. Breza, VUJE, Inc., Slovakia |
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Impact of the Alternative Fuel Cycles on the Long Term Safety of Deep Geological Repository, J. Prítrský, F. Ondra, DECONTA, Slovakia |
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12:30 - 13:30 Lunch |
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13:30 Technical excursion |
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19:30 Official dinner |
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Friday |
Topic 7: |
7.6 |
Meeting of Energy Needs During the Period of Raw Materials Insufficiency in the 21st Century (Bulgaria, Czech Republic, Poland, Russia and Slovakia cooperation – draft of project), V. Lelek, T. Apostolov, B. Petrov, S. Chwaszcewski, K. Andrzejewski, S. Subbotin, V. Tsibulskij, P. Darilek, R. Zajac, J. Breza |
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Uranium as Raw Material for Nuclear Energy, V. Lelek, NRI Řež plc., Czech Republic |
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Application of KARATE to Supercritical Water Reactors, Gy. Hegyi, Cs. Maráczy, KFKI Atomic Energy Research Institute, Hungary |
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Cofee break |
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10:30 Discussion and Symposium Closure |
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12:30 - 13:30 Lunch |
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Friday |
Poster Session |
- 12:30 |
Radiotoxicity of Thorium fuel cycle, J. Bajan |
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Infinite Multiplication Factor and Temperature Coefficient of MSR Calculated by HELIOS, Z. Németh |
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Electrodeposition of Lanthanum from Fluoride Melts, M. Ambrová, V. Danielik, J. Jurišová |
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Phase Diagrams of the Systems MF – La2O3 and M3AlF6 - La2O3 where M = Li, Na, K, M. Ambrová, V. Danielik, J. Jurišová |
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Dose Rate Calculation on the Surface of the C30 Container, B. Ecker, P. Lipták |