16th Symposium of AER on VVER Reactor Physics and Reactor Safety

Date: 2006-09-25 -- 2006-09-29

Place: Bratislava, Slovakia

Organized by: VUJE / FEEI SUT

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Welcome address

Welcome address
Marta Žiaková / Slovak Regulatory Authority / Slovakia
Welcome address
Vladimír Nečas / Faculty of Electrical Engineering and Information Technology / Slovak University of Technology / Slovakia
Welcome address
Vladimír Slugeň / Slovak Nuclear Society / Slovakia
Welcome address
Peter Líška / VUJE, Inc. / Trnava / Slovakia
Present Status of the Project „Modernization of NPP V2 Bohunice“
Pavol Ševera / VUJE, Inc. / Trnava / Slovakia
Mochovce NPP Units 3&4 - construction completion
Ivan Čillík, Štefan Rohár / VUJE, Inc. / Trnava / Slovakia

Spectral and Core Calculations

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. / Orlík 266, 31606 Plzeň / Czech Republic
Inclusion of Historical Dependences of Fuel Burn-up into MOBY-DICK Code
V. Krýsl, P. Mikoláš / ŠKODA JS a.s. / Orlík 266, 31606 Plzeň / Czech Republic
Quantitative and Quality Test of Cross Section Library ENDF/B-b2
R. Zajac / VUJE, Inc. / V. Nečas / FEEI SUT / Slovakia
BIPR7 Library Preparation by HELIOS
P. Dařílek / VUJE, Inc. / Slovakia
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

Core Operation, Experiments and Code Validation

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
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
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
Tests in “Kurchatov Institute” on Research of Coolant Mixing in Fuel Exit Channel of VVER-440 Reactor,
L. Kobzar, D. Oleksu / RRC “Kurchatov Institute” / Russia
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
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

Fuel Management

AER Working Group “B” Activities in 2006
P. Dařílek / VUJE, Inc. / Slovakia
Comparison of Optimizing Loading Patterns on the Basis of SA and PMA Algorithms
B. Beliczai / Paks NPP Ltd / Hungary
Gd-2 Fuel Cycle Benchmark - Final Definition
J. Bajgl / CEZ Inc. / Dukovany NPP / Czech Republic
Utilisation of Gd-2 Fuel Assemblies at NPP Bohunice Unit 3 and 4
M. Kačmar et al / Bohunice NPP / Slovakia
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
Results of Research and Optimization for the Third-Generation Fuel Assemblies PK-3 VVER-440
A. Gagarinskiy, A. Lazarenko, M. Lizorkin, B. Saprykin / RRC “Kurchatov Institute” / Russia
236U Compensation in Recycled Uranium Fuel for the VVER Reactors
V. Yu. Plyashkevich, V.N. Proselkov / RRC “Kurchatov Institute” / Russia
Stationary TVSA Fuel Cycles at Kozloduy NPP WWER-1000 Reactors
K. Kamenov / Kozloduy NPP Plc. / Bulgaria

Core Surveillance and Monitoring

AER Working Group C activity in 2006
Imre Nemes / Paks NPP Ltd / Hungary
Influence of Sampling Interval Inaccuracy on Calculated Reactivity Error
M. Sedlacek, M. Eľko / VUJE, Inc. / Slovakia
Modernization of In-Core Instrumentation System (ICIS) on Reactor VVER-1000
V. Mitin / RRC “Kurchatov Institute” / Russia
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
Application of New Methodology of Form-Functions Calculations in SCORPIO-VVER System
J. Šůstek / ŠKODA JS a.s. / Czech Republic
An advanced tool of nuclear reactor core analysis for reactor physicist: VERONA-expert system
István Pós, Zoltán Kálya, Gábor Farkas / Paks NPP Ltd / Hungary
A new Type of In-Core Sensor Validation Outline
S. Figedy / VUJE, Inc. / Slovakia
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
The Evaluation of Control Assembly Withdrawal by Dynamic Method - Practice Utilization
C. Strmenský, M. Minarčin, V. Petényi / VUJE, Inc. / Slovakia
Measurement and Evaluation Systems for NPP Commissioning
M. Eľko / VUJE, Inc. / Slovakia

Reactor Dynamics, Thermal Hydraulics and Safety Analysis

"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
Spectral Element Code Development for Incompressible Flow Simulations In the Subchannel of a Fuel Rod Bundle
P. Kávrán / KFKI Atomic Energy Research Institute / Hungary
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
State of the Art Regarding the Safety Analysis of Boron Dilution Events in Germany
S. Kliem, U. Rohde / Forschungszentrum Rossendorf / Germany
Uncertainty Analysis for Hot Channel
I. Panka, A. Keresztúri / KFKI Atomic Energy Research Institute / Hungary
Evaluation of Fuel Rod Cladding Failure
B. Hatala / VUJE, Inc. / Slovakia
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
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
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
The CFD Modeling of Coolant Flow in Fuel Assembly - Current Results and Their Application
K. Klučárová, J. Remiš / VUJE, Inc. / Slovakia

Physical Problems of Spent Fuel Decommissioning and Radwaste

Summary of Working Group „E“
V. Chrapčiak / VUJE, Inc. / Slovakia
The Analyses of Measured Nuclide Concentration in Project ISTC 2670
V. Chrapčiak / VUJE, Inc. / Slovakia
Composition Calculations by the KARATE Code System for the Spent-Fuel Samples from the Novovoronezh Reactor,
G. Hordósy / KFKI Atomic Energy Research Institute / Hungary
Validation of SCALE Depletion Calculations Against VVER Experimental Data,
M. Manolova, N. Mihaylov, M. Peeva, / INRNE, / Bulgaria (paper only)
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)
Methodology for Burnup Credit Application for VVER-440 Reactors in Slovakia
V. Chrapčiak / VUJE, Inc. / Slovakia
Bounding Approach in BUC Implementation in Pool at VVER-440,
F. Havlůj / NRI Řež plc / Czech Republic
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
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

Actinide Transmutation and Spent Fuel Disposal

Information about Activities AER Working Group “F” – Spent Fuel Transmutations
V. Lelek / NRI Řež plc. / Czech Republic
Sustainable Fuel Cycle Alternatives for Slovakia - Evaluation Methods
P. Dařílek / VUJE, Inc. / Slovakia
PWR and VVER Thorium Cycle Calculation
J. Breza / VUJE, Inc. / Slovakia
Fuel Research in Halden
J. Breza, P. Dařílek / VUJE, Inc. / Slovakia
Impact of the Alternative Fuel Cycles on the Long Term Safety of Deep Geological Repository
J. Prítrský, F. Ondra / DECONTA / Slovakia
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
Uranium as Raw Material for Nuclear Energy
V. Lelek / NRI Řež plc. / Czech Republic
Application of KARATE to Supercritical Water Reactors
Gy. Hegyi, Cs. Maráczy / KFKI Atomic Energy Research Institute / Hungary

Discussion and Symposium Closure