18th Symposium of AER on VVER Reactor Physics and Reactor Safety

Date: 2008-10-06 -- 2008-10-10

Place: Eger, Hungary

Organized by: MVM Paks

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Fuel cycles , uncertainty calculations

VVER-440 Fuel Cycles Possibilities Using Improved FA design
Pavel Mikoláš, Jiří Švarný, Czech Republic, SKODA JS a.s.
Lessons learned from the first 25 reloads on Paks Unit 1
Imre Nemes, Hungary, NPP Paks Ltd.
[95/95] APPROACH FOR DESIGN LIMITS ANALYSIS IN VVER
Shishkov L., Tsyganov S., Russia, RRC "Kurchatov Institute"
Contribution to the Power Distribution Methodology Uncertainties Assessment
Jiří Švarný, Czech Republic, SKODA JS a.s.
ESTIMATION OF ENGINEERING FACTORS FOR FUEL BURNUP OF VVER
A. Gagarinski, S. Tsyganov, L. Shishkov, Russia, Russian Research Centre "Kurchatov Institute"

Spectral and Core Calculation

Information about AER WG A On Improvement, Extension and Validation of Parameterized Few-Group Libraries for VVER 440 and VVER 1000
Pavel Mikoláš, Czech Republic, ŠKODA JS a.s.
Advanced Nodal Diffusion code for Reactor Analysis: Status of development
AR. Josek, L. Klecka, V. Stary, R. Vocka, J. Vysoudil, Czech Republic, Nuclear Research Institute Řež
DEVELOPMENT OF THE CODE-PACKAGE KASKAD FOR CALCULATIONS OF VVER
Bolobov P., Lazarenko A., Tomilov M., Russia, RRC "Kurchatov Institute"
WWER-440 CRITICALITY CALCULATIONS USING MCNP5 CODE
Gabriel Farkas, Ján Haščík, Matúš Stacho, Alena Vankova, Slovakia, Slovak University of Technology
Solution of the new Dukovany Benchmark using the new version of KARATE-440 code
György Hegyi, András Keresztúri, Csaba Maráczy, Hungary, KFKI Atomic Energy Research Institute
Diffusion model development in C-PORCA code concerning Gd-2 fuel application at NPP Paks
István Pós, Tamás Parkó, Hungary, Hungary, NPP Paks Ltd.
IMPLEMENTATION OF THE NEUTRONICS MODEL OF HEXTRAN/HEXBU-3D INTO APROS FOR VVER CALCULATIONS
Jukka Rintala, VTT, Finland
Calculation of neutron flux density distribution in VVER 440 reactor pressure vessel using MCNP5
M. Stacho, G. Farkas, V. Slugeň, S. Sojak, Slovakia, Slovak University of Technology
MEASUREMENTS BY ACTIVATION FOILS AND COMPARATIVE COMPUTATIONS BY MCNP CODE
Jan Kyncl, Czech Republic, Nuclear Research Institute Řež
The HELIOS-2 Lattice Physics Code
C.A. Wemple, H-N.M. Gheorghiu, R.J.J. Stamm'ler, E.A. Villarino, USA, Germany, Studsvik Scandpower, Inc
THE EFFECT OF SPATIAL DISCRETIZATION IN LWR CELL CALCULATIONS WITH HELIOS 1.9
B. Merk, R. Koch, Germany, Forschungszentrum Dresden-Rossendorf
CORE-WIDE CALCULATIONS BY HELIOS CODE
Sándor Patai-Szabó, Hungary, TS Enercon Ltd.
HELIOS2: Benchmarking Against Hexagonal Lattices
Charles Wemple and Teodosi Simeonov, USA, Germany, Studsvik Scandpower, Inc
PWR AND WWER MOX BENCHMARK CALCULATION BY HELIOS
Radoslav ZAJAC, Petr DARILEK, Vladimir NECAS, Slovakia, VUJE, Slovak University of Technology

Reactor Dynamics, Safety Analysis

AER WORKING GROUP D ON VVER SAFETY ANALYSIS - REPORT OF THE 2008 MEETING
S. Kliem, Germany, Forschungszentrum Dresden- Rossendorf
PRELIMINARY RESULTS OF CALCULATION OF THE INTERNATIONAL TEST PROBLEM v1000CT-1 WITH THE USE OF INTEGRAL THERMOHYDRAULIC COMPUTER CODE PACKAGES
G.V. Alekhin, G.L. Ponomarenko, S.A. Kurbaev, M.A. Bykov, USA, Russia, OKB "GIDROPRESS"
International Benchmark for Coupled Codes and Uncertainty Analysis in Modelling:Switching-off of one of the Four Operating Main Circulation Pumps at Nominal Reactor Power at NPP Kalinin Unit 3
V. A. Tereshonok, S. P. Nikonov, M. P. Lizorkin, K. Velkov, A. Pautz, K. Ivanov, USA,Russia, Germany, USA, VNIIAES, RRC "Kurchatov Institute", GRS mbH, The Pennsylvania State University
Accounting for the Inertia of the Thermocouples' measurements by Modelling of a NPP Kalinin-3 Transient with the Coupled System Code ATHLET-BIPR-VVER
S. Nikonov, K. Velkov, Russia, Germany, RRC "Kurchatov Institute", GRS mbH
Criticality Safety Analysis of the Incident Occurred at Paks NPP in 2003
András Wirth, Sándor Fehér, József Kópházi, Szabolcs Czifrus, Hungary, BME NTI
ANALYSIS OF THE SCRAM ACTUATION BY PERIOD DURING WWER-1000 FAST UNLOADING
Y.Ovdiienko, AKuchin, V.Khalimonchuk, Ukraine, (SSTC N&RS)
Possibilities of delayed neutron fraction (beff) calculation and measurement.
Svetozár Michálek, Ján Haščík, Gabriel Farkas, Slovakia, Slovak University of Technology

CFD, Hydraulic calculations

Working Group G activity in 2008.
A. Aszódi, BME NTI, Hungary
CFD Codes and the Onsager Relations
Mihály Makai, Hungary, BME NTI/ KFKI AEKI
Detailed analysis of coolant mixing in vver-440 fuel assembly heads
S. Tóth, A. Aszódi, Hungary, BME NTI
Hot channel calculation methodologies in case of Gd burnable poison
István Panka, András Keresztúri, Hungary, KFKI Atomic Energy Research Institute
Recent results of three-dimensional CFD simulations of coolant mixing in VVER-440/213 reactor pressure vessel
B. Kiss, I. Boros, A. Aszódi, Hungary, BME NTI

Physical problem of Spent Fuel, Decommissioning and Radwaste

AER Working Group E Meeting in 2008
Vladimir Chrapciak, L.Marková, Slovakia, Czech Republic, VUJE, UJV Rez
MODELING OF HISTORY EFFECTS IN BURNUP CALCULATIONS
Y. Bilodid, S. Mittag , Germany, Forschungszentrum Dresden-Rossendorf
VVER-1000 BURNUP CREDIT BENCHMARK (CB5). NEW RESULTS EVALUATION
Maria Manolova, Radostina Prodanova, Nikolay Mihaylov , Bulgaria, INRNE-BAS
An accurate synthetic algorithm for determining the time dependent Fission Gas Release (FGR) from the grain
András Keresztúri, Hungary, KFKI Atomic Energy Research Institute
Criticality Safety Analysis of the New Type Gd Fuel at Paks NPP
Gábor Hordósy, Hungary, KFKI Atomic Energy Research Institute
Radiation characteristics of Gd-2 fuel
Vladimír Chrapčiak, Slovakia, VUJE
Real burnup radial profile in the VVER-440 assembly (3.6% enrichment)
Vladimír Chrapčiak, Slovakia, VUJE
UPDATED RESULTS OF SIMPLIFIED BENCHMARK BASED ON #2670 ISTC VVER PIE
Frantisek HAVLUJ, Czech Republic, Nuclear Research Institute at Rez
Solution of the Dimitrovgrad Fuel Composition Benchmark with the KARATE-440 Code System
Gy. Hegyi, G. Hordósy, A. Keresztúri, Cs. Maráczy, E. Temesvári, Hungary, KFKI Atomic Energy Research Institute
DATABASE OF PUBLICLY AVAILABLE VVER PIE DATA
Frantisek HAVLUJ, Czech Republic, Nuclear Research Institute Rez
International consortium for PIE measurement of VVER-440 fuel
Vladimir Chrapciak, L.Marková , Slovakia, Czech Republic, VUJE, UJV Rez

Core Surveillance and Monitoring

Working Group C activity in 2008
Imre Nemes , Hungary, NPP Paks Ltd.
Demonstration of 1% accuracy for reactor power keeping at Mochovce NPP
Juraj Simko , Slovakia , Mochovce NPP
SIMULATION OF THE EXPERIMENT ON STUDYING XENON OSCILLATIONS AT KALININ NPP, UNIT 3
A.N. Ustinov, K.Yu. Kurakin, A.K. Gorokhov , Russia, OKB "GIDROPRESS"
Outlet temperature Measurement Correction of Gd fuel assemblies at Dukovany NPP
Monika Juříčková , Czech Republic , Nuclear Research Institute Rez
NEW SCORPIO-VVER WITH ADVANCED POWER RECONSTRUCTION AND LIMIT CHECKING
Jozef Molnár and Radim Vočka , Czech Republic, Nuclear Research Institute Řež
THE PROCEDURE FOR DETERMINATION OF SPECIAL MARGIN FACTORS TO ACCOUNT FOR A BOW OF THE VVER-1000 FUEL ASSEMBLIES
Tsyganov S.V., Marin S.V, Shishkov L.K., Russia, Russian Research Center "Kurchatov Institute"
Non-standard physics tests of AKNT-17R System COMMISSIONING at Bohunice NPP
Sedlacek M., Peternyi V., Slovakia, VUJE, Inc.

Actinide Transmutation and Spent Fuel Disposal

Information about meeting AER working group F "Transmutations" and connected INPRO IAEA Collaborative Projects CZE1 "Meeting energy needs in the period of raw materials insufficiency during the 21st century"
Vladimir Lelek, Czech Republic, Nuclear Research Institute Rez
Fast breeder for fuel material production
P. Vértes, Hungary, KFKI Atomic Energy Research Institute
HPLWR Phase 2 - Core Design
Csaba Maráczy, György Hegyi, Gábor Hordósy, Emese Temesvári, Csaba Hegedűs and Attila Molnár, Hungary, KFKI Atomic Energy Research Institute
TRANSMUTATION OF THE WWER-440 SPENT FUEL IN FAST REACTOR
Radoslav ZAJAC, Petr DARILEK, Vladimir NECAS, Slovakia, VUJE, Slovak University of Technology
Advanced fuel cycles options for LWRs and IMF benchmark definition
Juraj Breza, Petr DARILEK, Vladimir NECAS, Slovakia, VUJE, Slovak University of Technology
Suggestion of ways to analyze future energy needs and possibilities to cover them in participating countries - working plan for next several years.
Vladimir Lelek, Czech Republic, Nuclear Research Institute Rez

Core operation, Experiments and Code Validation

Working Group B activity in 2008.
P. Darilek, Slovakia, VUJE, Inc.
Comparisons between the measured and calculated by KASKAD neutron-physics characteristics of the cores WWER-1000/320 at Kozloduy NPP during the fuel campaign
Iskra Stoyanova, Bulgaria, Kozloduy NPP
PREPARING THE INITIAL NEUTRON PHYSICS DATA FOR JUSTIFICATION OF FUEL UNDER POWER VARIATION MODES. STATEMENT OF the PROBLEM AND EXPERIENCE IN PRACTICAL SOLUTION
K.Yu. Kurakin, B.G. Kozak, A.K. Gorokhov, Russia, OKB "GIDROPRESS"
EFFECT OF HEXBU-3D FEEDBACK AND BOUNDARY CONDITION MODELS ON THE CALCULATED REACTOR CORE CHARACTERISTICS OF LOVIISA NPP
Tuukka Lahtinen, Simo Saarinen, Martti Antila, Finland, Fortum Nuclear Services Ltd
CALCULATION OF THE CHANGE IN POWER DISTRIBUTION AROUND THE JOINING STRUCTURE OF THE ABSORBER AND FUEL PART OF THE WWER-440 CONTROL ASSEMBLY USING MCNP5 CODE
Gabriel Farkas, Vladimír Slugeň, Tomáš Melo, Slovakia, Slovak University of Technology
Gd benchmark calculations in VUJE
Juraj Breza, Pavol Čudrnák, Petr DARILEK, Slovakia, VUJE, Slovak University of Technology
Five years Fuel Cycle in Dukovany NPP
Josef Bajgl, Czech Republic, CEZ Inc., Dukovany NPP