19th Symposium of AER on VVER Reactor Physics and Reactor Safety

Date: 2009-09-21 -- 2009-09-25

Place: Varna, Bulgaria

Organized by: IRT

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Official opening of the Symposium

Opening speech - History of AER and lessons learned
István Vidovszky, KFKI AEKI, Hungary

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
Pavel Mikoláš, ŠKODA JS a.s., Czech Republic
Proposal of a Benchmark on core burnup follow calculations for a VVER-1000 reactor core
Tomas Lötsch, TÜV SÜD Industrie Service GmbH, Volodymyr Khalimonchuk, A. Kuchin, SSTC for Nuclear and Radiation Safety, Ukraine,
Full-scale model VVER-1000 of Monte-Carlo calculation of neutron characteristics in core. MCU’s and BIPR’s results comparison
S.S. Gorodkov, D.S. Oleynik, E.A. Sukhino-Khomenko, V.G. Dementiev, RRC “Kurchatov Institute”, Russia
VVER-1000 dominance ratio
S.S.Gorodkov, RRC “Kurchatov Institute”, Russia
HELIOS2: Benchmarking Against Experiments for Hexagonal and Square Lattices
Teodosi Simeonov, Studsvik Scandpower GmBH, Germany
On the problem of criticality with a feedback
Jan Kyncl, Nuclear Research Institute Řež, Czech Republic
2D core solutions for VVER-1000 with APOLLO2 and TRIPOLI4
G.Todorova, N.Petrov, N.P.Kolev, INRNE, Sofia, S.Santandrea, F-X.Hugot, SERMA, CEA Saclay
Progress in implementation of the neutronics model of HEXTRAN into APROS
Jukka Rintala, VTT, Finland

Core Operation, experiments and code validation

Neutron physics calculation for VVER-1000 control rod lifetime determination
Konstantin Kurakin, S.A. Kushmanov, EDO “GIDROPRESS”, Russia
Proposal for development of regulatory basis of engineering factor evaluation for the VVER core parameters
L.Shishkov, S.Tsyganov, V.Dementiev, RRC “Kurchatov Institute”, Russia
To the problem of the statistical basis of evaluation of the mechanical margin factor
S. Tsyganov, RRC “Kurchatov Institute”, Russia
Analysis of the methodical component of core power density field calculation error on the basis of Mohovce-1 commissioning tests
Alexander Brik, RRC “Kurchatov Institute”, Russia
VVER-440 Control Rod Follower Induced Local Power Peaking
Gy. Hegyi, G. Hordósy, A. Keresztúri, Csaba Maráczy, E. Temesvári, KFKI AEKI, Hungary
Computational Benchmark: MCNP and KARATE Solutions
Gy. Hegyi, G. Hordósy, A. Keresztúri, Csaba Maráczy, E. Temesvári, KFKI AEKI, Hungary

Fuel management

AER Working Group B Activities in 2009
Petr Darilek, VUJE Inc., Slovakia
Contemporary and prospective fuel cycles for VVER-440 based on new assemblies with higher uranium capacity and higher average fuel enrichment
A.A. Gagarinskiy, V.V. Saprykin, RRC “Kurchatov Institute”, Russia
Transition to Four Batch Loading Scheme in Loviisa NPP
S. Saarinen, T. Lahtinen, M. Antila, Fortum Nuclear Services Ltd, Finland
VVER-440 Loading Patterns Optimization Using Athena Code.
J. Bajgl, Dukovany NPP, R. Čada, University of West Bohemia, Karel Katovský, J. Šůstek, ŠKODA JS a.s., Czech Republic
VVER-440 Fuel Cycles Possibilities Using Modified FA Design
Pavel Mikoláš, Jiří Švarný, Vladislav Razým, Michal Dostál, Jiří Jeník, Pavel Krupař, ŠKODA JS a.s., Czech Republic
Basic Neutronphysical and Thermal-Hydraulic Characteristics of Five Years Fuel Cycle at Increased Power Level 1444MWth
Josef Bajgl, Dukovany NPP, Czech Republic
Contribution to the VVER-440 Gd-Assembly Evolution
Pavol Cudrnak, Petr Darilek, Vladimir Necas, VUJE Inc., Slovakia
Burning Plutonium and Minimizing Radioactive Waste in Existing PWR
Siegfried Mittag, Sören Kliem, Forschungszentrum Dresden, Germany
Experience of TVSA Fuel Implementation and KASKAD Code Package Validation at Kozloduy NPP
Krasimir Kamenov, Al.Kamenov, D. Hristov, NPP Kozloduy, Bulgaria

Core Surveillance and Monitoring

Reactor Core T-H Characteristics Determination in Case of Parallel Operation of Different Fuel Assembly Types
Jozef Hermansky, Vincent Petényi, Martin Závodský, VUJE, Inc., Slovakia
Results of Reactor Core Symmetry Measurements at Bohunice and Mochovce NPPs
M. Sedlacek, V. Petenyi, VUJE, Inc., Slovakia
Installation and commissioning of AKE-02R system (neutron power on-line calibration) at Bohunice NPP
Martin Závodský, Katarína Klučárová, VUJE, Inc., Slovakia
Results of Lead Test Program of Gd-2N fuel assemblies at Paks NPP
B. Beliczai, T. Parkó, Paks NPP Ltd., Hungary
SCORPIO-VVER Core Monitoring and Surveillance System with Advanced Capabilities
Jozef Molnár, NRI Řež, Czech Republic
Assembly thermo hydraulic model ASHYMO improvement for VERONA in-core monitoring system
Zs. Szécsényi, Cs. Szécsényi, Paks NPP Ltd., Hungary
Determination of Weight Factors for VVER-440 Fuel Assemblies with Burnable Poison
S. Tóth, A. Aszódi, Budapest University of Technology and Economics, Institute of Nuclear Techniques, Hungary
Fuel Assembly Leakage Unit 4, Cycle 22 of Paks NPP
Cs. Szécsényi, G. Bóna, B. Torma, T. Burján, Paks NPP Ltd., Hungary
Monte Carlo Calculations of Neutron Fields in VVER-440 Reactor Pressure Vessel
Matúš Stacho, Slovak University of Technology, Slovakia

Reactor Dynamics, Thermal Hydraulics and Safety Analysis, CFD Analysis

AER Working Group D on VVER Safety Analysis – Report of the 2009 Meeting
Soeren Kliem, Forschungszentrum Dresden, Germany
Prediction of measured SPND readings with the coupled code system ATHLET-BIPR-VVER
S.Nikonov, K.Velkov, A.Pautz, RRC “Kurchatov Institute”, Russia
3D grid for calculation of the coolant’s parameters distribution in the reactor’s volume
S.Nikonov, RRC “Kurchatov Institute”, Russia
Lessons learned from the OECD VVER-1000 coolant mixing and MSLB benchmark
N. Kolev, INRNE-BAS, Bulgaria, E.Royer, CEA Saclay, E.Sartori, OECD/NEA
COBAYA3 and CRONOS Solutions of the V1000CT2-EXT2 Benchmark
I.Spasov, INRNE-BAS, J. Jimenez, J.A. Lozano, J.J. Herrero, Universidad Politecnica de Madrid, N. Kolev, INRNE-BAS, Bulgaria
Conservative RIA analysis with use of spatial kinetic model
Iurii Ovdiienko, SSTC for Nuclear and Radiation Safety, Ukraine
Investigations on Accident Management Measures for VVER-1000 Reactors
Polina Tusheva, Frank Schäfer, Nils Reinke, Ulrich Rohde, Forschungszentrum Dresden, Germany
First results on the effect of fuel-cladding eccentricity
István Panka, András Keresztúri, KFKI AEKI, Hungary
Transient calculations of coolant mixing in VVER-440/213 type RPV
Béla Kiss, Ildikó Boros, Attila Aszódi, Budapest University of Technology and Economics, Institute of Nuclear Techniques, Hungary
VVER-440 Fuel Assembly Head CFD Benchmark
A. Aszódi, S. Tóth, Budapest University of Technology and Economics, Institute of Nuclear Techniques, Hungary
CFD study on coolant mixing inside VVER-440 fuel rod Bundle
Tellervo Brandt, Fortum Nuclear Services Ltd, Finland
Solution of the OECD NEA Kalinin-3 Coolant Transient Benchmark Phase 1 Problem by Using the ATHLET Code
István Trosztel, Sergey Nikonov, György Hegyi, András Keresztúri, KFKI AEKI, Hungary

Physical problems of Spent Fuel, Decommissioning and Radwaste

AER Working group E in 2009
Vladimir Chrapciak, VUJE, Inc., Trnava, Slovakia
SCALE 6 - Crtiticality Calculation for VVER-440 Fuel
Vladimir Chrapciak, VUJE, Inc., Trnava, Slovakia
BUC Implementation in Slovakia
Vladimir Chrapciak, VUJE, Inc., Trnava, Slovakia
Nuclear libraries for SCALE5.1 system
Péter Vértes, MTA AEKI, Hungary
Burnup credit calculation
Gábor Hordósy, KFKI AEKI, Hungary
Burnup Influence on the Neutron Fluence of VVER-1000 Reactor Vessel
Ivaylo Panayotov, Nikolay Mihaylov, Krassimira Ilieva, Desislava Kirilova, Maria Manolova, INRNE-BAS, Bulgaria

Actinide Transmutation and Spent Fuel Disposal

Information about 12th session of AER working group F “Transmutations” and INPRO activities
Vladimir Lelek, NRI Řež, Czech Republic
The Pu Re-using in the Fast Reactor under Slovak Conditions
Radoslav Zajac, Petr Darilek, Vladimir Necas, VUJE, Inc., Trnava, Slovakia
Alternative Thorium Fuel Cycle for LWRs
Juraj Breza, Peter Cudrnak, Petr Darilek, Vladimir Necas, VUJE, Inc., Trnava, Slovakia
Future fuel cycle closing by molten salt reactors
Vladimir Lelek, NRI Řež, Czech Republic
Problems of energy supply planning
Vladimir Lelek, NRI Řež, Czech Republic