17th Symposium of AER on VVER Reactor Physics and Reactor Safety

Date: 2007-09-23 -- 2007-09-29

Place: Yalta, Crimea (Ukraine, back then)

Organized by: SSCT N&RS / RRC KI

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OPENING PANEL AND INVITED SPEAKERS' PRESENTATIONS

PRIORITY PROGRAMS OF NUCLEAR POWER BRANCH IN RUSSIA
Asmolov V.G., Rosenergoatom
LEGISLATIVE BASIS OF NUCLEAR ENERGY DEVELOPMENT IN UKRAINE
Bronnikov V. K., People's Deputy, Chairman of the Verkhovna Rada Subcommittee on Nuclear Policy and Nuclear Safety of Ukraine
PROSPECTS OF NUCLEAR INDUSTRIAL COMPLEX DEVELOPMENT IN UKRAINE
Yurii Nedashkovsky, Ministry for Fuel and Energy of Ukraine

FUEL MANAGEMENT

EXPERIENCE OF FUEL OPERATION AT RUSSIAN NPPS
N.M. Sorokin, Yu.V. Kopyov, V.E. Khlentsevich, A.K. Egorov, Rosenergoatom
ADVANCED FUEL CYCLES FOR VVER-1000 REACTORS
Semchenkov Yu.M., Pavlovichev A.M., Pavlov V.I., Spirkin E.I. and Styrin Y.A. Kosourov E.K., RRC "Kurchatov Institute", Moscow, Russia
EXPERIENCE IN RUSSIAN FUEL ASSEMBLIES IMPLEMENTATION AT SUNPP-2<
N.N. Stepanov, V.N. Zhestkov Nuclear Safety Department of SUNPP
BURNUP INCREASE AND FUEL USE IMPROVEMENT AT THE KALININ NUCLEAR POWER PLANT UNITS WITH TVSA FUEL ASSEMBLIES
Samoilov O.B., Romanov A.I., Peskov R.A. OKBM Pavlovichev A.M., Spirkin E.I., Pavlov V.I. RRC "Kurchatov Institute", Moscow, Russia Lupishko A.N., Makarov S.V., Chapaev V.M. Kalinin NPP
EXTENSION OF VVER-440 FUEL CYCLES USING IMPROVED FA DESIGN
Pavel Mikolas, Jiri Svarny SKODA JS a.s.
RECENT CORE DESIGN AND OPERATING EXPERIENCE IN LOVIISA NPP
M. Antila, T. Lahtinen Fortum Nuclear Services Ltd, Espoo, Finland
FUEL PERFORMANCE AND OPERATION EXPERIENCE OF VVER-440 FUEL IN IMPROVED FUEL CYCLE
A. Gagarinski, V. Proselkov, RRC "Kurchatov Institute", Moscow, Russia
TRANSIENT AND EQUILIBRIUM CYCLE CHARACTERISTICS ON PAKS UPRATED POWER UNITS 2ND GENERATION OF GADOLINIA FUEL
Nemes Imre NPP Paks, Hungary
DUKOVANY NPP - FUEL CYCLE DEVELOPMENT
Josef Bajgl CEZ Inc., Dukovany NPP, Czech Republic
FUEL CYCLES OF VVER-440 [poster]
V.V. Saprykin, I.I. Yasnopolskaya, A.N. Novikov RRC "Kurchatov Institute", Moscow, Russia
SAFETY AND DESIGN LIMITS
Shishkov L.K., Gorbaev V.A., Tsyganov S.V. RRC "Kurchatov Institute", Moscow, Russia
CURRENT TASKS OF THE STATE NUCLEAR REGULATORY COMMITTEE OF UKRAINE
Mikhail Gashev State Nuclear Regulatory Committee of Ukraine
IMPACT OF CHANGED FUEL PERFORMENCES ON SAFETY BARRIERS EFFECTIVNESS AT NORMAL OPERATION OF NPP WITH VVER
Zhurbenko A.V, Semchenkov Yu.M., Slavyagin P.D. RRC "Kurchatov Institute", Moscow, Russia
SEVERAL REMARKS ON THE FUEL CYCLE ECONOMY
Roman Kubin, Rudolf Vespalec ALTA, a.s., Czech Republic
PROBLEMS OF FUTURE ENERGY MARKET PLANNING AND OPTIMIZATION
Vladimir Lelek, David Jaluvka Nuclear Research Institute Rez, Czech Republic

SPECTRAL AND CORE CALCULATION

INFORMATION ABOUT AER WG A ON IMPROVEMENT, EXTENSION AND VALIDATION OF PARAMETRIZED FEW-GROUP LIBRARIES FOR VVER 440 AND VVER 1000
Pavel Mikolas SKODA JS a.s.
INNOVATIONS IN MOBY-DICK CODE
Josef Sustek, Vaclav Krysl SKODA JS a.s.
COMPARISON OF CASMO AND NESSEL FEW GROUP CROSS SECTION LIBRARIES AND THEIR USAGE IN DYN3D
A. Kuchin, Y.Ovdienko, State scientific and technical center on nuclear and radiation safety, Kiev, Ukraine T.Loetsch TUV SUD, Munchen, Germany
PERMAK-3D/SC-1 PIN-BY-PIN NEUTRON-THERMOHYDRAULIC COMPUTER CODE SYSTEM FOR 3D ANALYSIS OF VVER CORE
P.Bolobov, D.Oleksyuk RRC "Kurchatov Institute", Moscow, Russia
CALCULATION OF THE REACTOR PHYSICS AND THERMAL MECHANICS CHARACTERISTICS OF THE FUEL RODS NEXT TO THE VVER-440 ABSORBER ASSEMBLY
A. Kereszturi, A. Griger, Cs. Maraczy, Gy. Hegyi, G. Hordosy, E. Temesvari KFKI Atomic Energy Research Institute
THE THERMAL-MECHANICAL BEHAVIOR OF FUEL PINS DURING POWER'S MANEUVERING REGIME AT STATIONARY CORE LOADING ON 2ND UNIT OF KHNPP
M. Ieremenko, Y.Ovdiyenko, V.Khalimonchuk State Scientific and Technical Centre on Nuclear and Radiation Safety (SSTC N&RS)
VVER CORE TEST MODEL
A.V. Tikhomirov, A.K. Gorokhov, OKB "GIDROPRESS", Podolsk, Russia
DIFIS 2.0 - 3D FINITE ELEMENT NEUTRON KINETIC CODE
A.I.Zhukov and A.M.Abdullayev, NSC Kharkov Institute of Physics and Technology
CODES COMPLEX FOR QUICK TRANSPORT 3D NEUTRON CALCULATIONS OF VVER
Laletin N.I., Kovalishin A.A., Sultanov N.V., Laletin M.N. RRC "Kurchatov Institute", Moscow, Russia
COMPARATIVE STOHASTIC - DETERMINISTIC 2D CALCULATIONS OF VVER CORES
S.S.Gorodkov, E.A.Suhino-Homenko RRC "Kurchatov Institute", Moscow, Russia
ACCELERATING OUTER ITERATIONS IN MULTIGROUP PROBLEMS ON K[eff]
G. Kurchenkova and V. Lebedev RRC "Kurchatov Institute", Moscow, Russia
PROPOSAL OF THE TEST PROBLEM ON POWER DISTRIBUTION VS INTERASSEMBLY GAP
Dementiev V.G., Gomin E.A., Marin S.V., Tsyganov S.V., Shihkov L.K. RRC "Kurchatov Institute", Moscow, Russia
HIGH PERFORMANCE LIGHT WATER REACTOR CORE CALCULATIONS
Cs. Maraczy, Gy. Hegyi, G. Hordosy, E. Temesvari KFKI Atomic Energy Research Institute, Budapest, Hungary

CORE SURVEILLANCE AND MONITORING. CFD ANALYSIS

INFORMATION ABOUT AER WG C AND G ACTIVITY
I. Nemes, NPP Paks
STATISTICAL EVALUATION OF THE ON-LINE CORE MONITORING EFFECTIVENESS FOR LIMITING THE CONSEQUENCES OF THE FUEL MISLOADING EVENT
A. Molnar, A. Kereszturi, E. Temesvari KFKI Atomic Energy Research Institute, Budapest, Hungary
MODERN IN-CORE MONITORING SYSTEM FOR HIGH-POWER REACTOR
Mitin V.I., Alexeev A.N., Kalinushkin A.E., Kovel A.I., Milto N.V., Musikhin A.M., Tikhonova N.V. RRC "Kurchatov Institute", Moscow, Russia
DETECTING OF COOLANT BOILING IN VVER-1000 CORE ON THE BASE OF NEUTRON FLUX NOISE DUE TO FLUCTUATIONS OF COOLANT PARAMETERS
Semchenkov Yu.M., Milto V.A., RRC "Kurchatov Institute", Moscow, Russia Pinegin A.A., Shumsky B.E. Moscow State Power-Engineering Institute (State University), Moscow
MODELLING OF THE WWER-440 REACTOR FOR DETERMINATION OF THE SPATIAL WEIGHT FUNCTION OF EX-CORE DETECTORS USING MCNP-4C2 CODE
Gabriel Farkas, Vladimir Slugen Slovak University of Technology, Bratislava, Slovakia
IMPLEMENTATION OF UKRAINIAN NPP WWER-1000 INCORE MONITORING SYSTEM ENHANCEMENT CONCEPTION BASED ON “KRUIZ” SOFTWARE
A.V.Bykov "Innovative company SNIIP Atom" LTD
ESTIMATION OF OPERATING FACTORS AND ERRORS OF MODEL INFLUENCE ON PRECISION OF "KRUIZ" SOFTWARE POWER DISTRIBUTION REBUILDING ALGORITHM ON THE EXAMPLE OF UNIT 4 ROVNO NPP
A.V.Bykov, T.A.Makarova "Innovative company SNIIP Atom" LTD
BASIS AND ALOGORITMS APPLIED IN MODERN NEUTRON FLUX MONITORING EQUIPMENT FOR VVER. SOME RESULTS OF ITS OPERATION
Alpatov A.N., Kamyshan A.N. RRC "Kurchatov Institute", Moscow, Russia Louzhnov A.M., Sokolov I.V. JSC "SNIIP-SYSTEMATOM"
SUNPP REACTOR CORE PARAMETERS SURVEILLANCE
A.L. Arvaninov. Nuclear Safety Department, South-Ukraine NPP
OUTLET TEMPERATURE MEASUREMENT COMPARISON OF GD AND NON GD FUEL ASSEMBLIES AT DUKOVANY NPP
Monika Jurickova Nuclear Research Institute Rez
RADIATION HEATING OF THERMOCOUPLE ABOVE FUEL ASSEMBLY
Javor Erika NPP Paks, HUNGARY
ASSEMBLY SUB CHANNEL MODEL IMPROVEMENT FOR THE VERONA IN CORE MONITORING SYSTEM
Zsolt Szecsenyi NPP of Paks, Hungary
PRELIMINARY VALIDATION OF VVER-440 FUEL ASSEMBLY HEAD CFD MODEL
S. Toth, A. Aszodi Budapest University of Technology and Economics , Institute of Nuclear Techniques
ANALYSIS OF MIXING PROCESSES IN VVER-440 ROD BUNDLE WITH RANS METHOD
S. Toth, A. Aszodi Budapest University of Technology and Economics , Institute of Nuclear Techniques
USE OF CFD-CODE PHOENICS FOR THERMOHYDRAULIC CALCULATIONS OF VVER CORE
L.L. Kobzar, D.A. Oleksyuk, A.A. Shestakov RRC "Kurchatov Institute", Moscow, Russia
THE INFLUENCE OF OUTLET TEMPERATURE PROFILE ON FUEL ASSEMBLY POWER DETERMINATION
K. Klucarova, J. Remis, M. Zavodsky, V. Petenyi VUJE, Inc., Slovak Republic
PRE-TEST CFD SIMULATIONS OF GIDROPRESS MIXING FACILITY EXPERIMENTS USING ANSYS CFX
T. Hohne, U. Rohde Forschungszentrum Dresden- Rossendorf (FZD), Institute of Safety Research Daniele Melideo, Fabio Moretti Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione, Universita di Pisa (UNIPI) A.Shishov, E.Lisenkov FSUE OKB Gidropress
USING DNS METHODS FOR NUMERICAL SIMULATION OF THERMAL-HYDRAULIC EFFECTS IN FUEL ROD BUNDLES
Yu. V. Yudov, Alexandrov Research Institute of Technology, Sosnovy Bor, Leningrad region, Russia

REACTOR DYNAMICS, THERMAL HYDRAULICS AND SAFETY ANALYSIS

AER WORKING GROUP D ON VVER SAFETY ANALYSIS - REPORT OF THE 2007 MEETING
S. Kliem Forschungszentrum Dresden-Rossendorf, Institute of Safety Research
MODELING OF THERMAL-COUPLES' MEASUREMENTS AT CORE EXIT OF REACTOR VVER-1000 WITH THE COUPLED SYSTEM CODE ATHLET-BIPR-VVER
S. Nikonov1, M. Lizorkin1, A. Kolychev2, S. Langenbuch3, K. Velkov3 1 RRC "Kurchatov Institute", Moscow, Russia 2 Atomtechenergo, Moscow , Russia 3 GRS mbH, Garching, Germany
ADVANCED ANALYSIS OF THE CEA-NEA/OECD VVER-1000 COOLANT TRANSIENT BENCHMARK WITH THE COUPLED SYSTEM CODE ATHLET-BIPR-VVER
S. Nikonov, M. Lizorkin RRC "Kurchatov Institute", Moscow, Russia S. Langenbuch, K. Velkov GRS mbH, Garching, Germany
MODELING OF NPP WITH VVER-1200 BY THE COUPLED SYSTEM CODE ATHLET/BIPR-VVER USING QUASI 3D NODALISATION OF REACTOR PRESSURE VESSEL AND STEAM GENERATORS
A. Kotsarev, M. Lizorkin, S. Danilin RRC "Kurchatov Institute", Russia S. Langenbuch and K. Velkov GRS mbH, Germany
COMPARATIVE ANALYSIS OF DIFFERENT METHODS OF MODELING OF MOST LOADED FUEL PIN IN TRANSIENTS
Y.Ovdiyenko, V.Khalimonchuk, M.Yeremenko State Scientific and Technical Centre on Nuclear and Radiation Safety (SSTC N&RS)
DEVELOPMENT STATUS AND APPLICATIONS OF THE KORSAR SYSTEM COMPUTER CODE
Yu.A. Migrov and Yu.V. Yudov Alexandrov Research Institute of Technology, Sosnovy Bor, Leningrad region
ANALYSIS AND DEVELOPMENT OF THE AUTOMATED EMERGENCY ALGORITHM TO CONTROL PRIMARY TO SECONDARY LOCA ACCIDENT FOR SUNPP SAFETY UPGRADING
V. Kim, V. Kuznetsov, G. Balakan, G. Gromov, I. Lola, S. Sholomitsky, A.Krushynsky Analytical Research Bureau for Nuclear Safety
ANALYTICAL INVESTIGATION OF FUEL COOLING CONDITIONS IN WWER-440 SPENT FUEL POOL DURING TRANSIENT CAUSED BY FAILURES IN THE COOLING SYSTEM
Alekseev Y.P. Gromov G.V. Lyssenko S.V. Shikhabutinov V.E. Sholomitsky S.E. Analytical Research Bureau for Nuclear Safety

PHYSICAL PROBLEM OF SPENT FUEL, DECOMMISSIONING AND RADWASTE

SUMMARY OF WORKING GROUP E IN 2007
Vladimir Chrapciak VUJE, a.s
SCALE 5.1 - CRITICALITY AND INVENTORY CALCULATION FOR VVER-440 FUEL
Vladimir Chrapciak VUJE, a.s
USE OF THE AXIAL BURNUP PROFILE AT THE NUCLEAR SAFETY ANALYSIS OF THE VVER-1000 SPENT FUEL STORAGE IN UKRAINE
O.Dudka, Y.Bilodid, Y.Kovbasenko, V.Khalimonchuk State Scientific and Technical Centre on Nuclear and Radiation Safety (SSTC N&RS)
WWER-1000 SPENT FUEL NUCLIDE INVENTORY AT THE KOZLODUY NPP
Krasimir Kamenov Kozloduy NPP
SIMPLIFIED BENCHMARK BASED ON #2670 ISCT VVER PIE SPECIFICATION AND PRELIMINARY RESULTS
F. Havluj, L. Markova Nuclear Research Institute, Rez, Czech Republic
COMPARATIVE ANALYSIS OF NUCLEAR SAFETY OF REGULAR AND COMPACT SPENT FUEL STORAGE ON CHORNOBYL NPP
Y.Kovbasenko, Y.Bilodid, V.Khalimonchuk, State Scientific and Technical Center for Nuclear and Radiation Safety, A.Novikov, E.Lebedev, D.Cherkas, State specialized enterprise "Chornobyl NPP"

ACTINIDE TRANSMUTATION AND SPENT FUEL DISPOSAL

INFORMATION ABOUT THE AER WORKING GROUP F "TRANSMUTATIONS"
Vladimir Lelek Nuclear Research Institute Rez, Czech Republic
PLUTONIUM AND MA MANAGEMENT IN VVER-440 AND FR
Petr Darilek, Radoslav Zajac VUJE Inc., Trnava, Slovakia Juraj Breza, Vladimir Necas Slovak University of Technology Bratislava, Bratislava, Slovakia
PLUTONIUM TRANSMUTATION IN THORIUM FUEL CYCLE
Juraj Breza1,2, Petr Darilek1, Vladimir Necas2 1 VUJE Inc., Trnava, Slovakia 2 Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Bratislava, Slovakia
FAST MOLTEN SALT REACTOR-TRANSMUTER FOR CLOSING NUCLEAR FUEL CYCLE ON MINOR ACTINIDES
A.A.Dudnikov, P.N.Alekseev, S.A.Subbotin RRC "Kurchatov Institute", Russia
USE OF VVER SPENT FUELS IN A THORIUM FAST BREEDER
P. Vertes, KFKI Atomic Energy Research Institute, Budapest, Hungary

CORE OPERATION, EXPERIMENTS AND CODE VALIDATION

AER WORKING GROUP B ACTIVITIES IN 2007
Petr Darilek VUJE Inc., Trnava, Slovakia
THE EXPERIENCE OF VVER-1000 REACTOR CORE POWER DISTRIBUTION CONTROL IN THE MODE OF POWER CHANGES
Korinny Andriy Khmelnitskaja NPP
VVER-1000 LOAD-FOLLOW CONDITIONS SIMULATION
A.N. Ustinov, K.Yu. Kurakin, A.K. Gorokhov OKB "GIDROPRESS", Podolsk, Russia
USE OF UNITS WITH VVER-1000 FOR MAINTENANCE OF BALANCE OF POWER SYSTEM
V.E. Baskakov21, M.V. Maksimov2, O.V. Maslov2 1 Zaporizhzhya NPP, Energodar, Ukraine 2 Odessa National Polytechnic University, Odessa, Ukraine
COMPARISON OF THE APA-H (WESTINGHOUSE) CALCULATIONS WITH THE OPERATIONAL DATA FOR ZpNPP UNIT #3 CYCLES 16-19
A.M.Abdullayev, O.V.Gorbachenko*, A.I.Ignatchenko*, S.V.Maryokhin, A.I.Zhukov, NFC STE NSC KIPT, Kharkov, Ukraine *Zaporozhye NPP, Energodar Ukraine
VERIFICATION OF SAPFIR_95&RC CODE PACKAGE AGAINST OPERATIONAL DATA OF VVER UNITS
Yu.A. Ananyev, K.Yu. Kurakin OKB "GIDROPRESS", Podolsk, Russia
COMPARISON OF CALCULATED AND MEASURED FA RELATIVE POWERS AT KOLA NPP UNITS 3 AND 4
A. Brik RRC "Kurchatov Institute", Moscow, Russia
SENSITIVITY ANALYSIS AND VERIFICATION OF FUEL ROD MODEL USED IN COUPLED NEUTRONIC AND THERMAL-HYDRAULIC CODES
L.M. Artemova, V.G. Artemov, and Yu.P. Shemayev Alexandrov Research Institute of Technology, Sosnovy Bor, Russia
SOME NEW EXPERIENCE WITH ZR-6 MEASUREMENTS USING DIFFERENT CODE SYSTEMS
Gy. Hegyi KFKI Atomic Energy Research Institute Reactor Analysis Laboratory, Budapest, Hungary
START UP PHYSICS TESTS OF UNITS 5&6 (WWER1000) AT KOZLODUY NPP BY COMPARISON WITH THE CALCULATED NEUTRON PHYSICS CHARACTERISTICS
A. Antov, I. Stoyanova Kozloduy NPP
INFLUENCE OF DELAYED NEUTRON PARAMETERS CALCULATION ACCURACY ON RESULTS OF MODELED VVER SCRAM EXPERIMENTS
V.G. Artemov, V.I. Gusev, R.E. Zinatullin, and A.S. Karpov Alexandrov Research Institute of Technology, Sosnovy Bor, Russia
STATISTICAL ANALYSIS OF DYNAMIC PARAMETERS OF THE CORE
Ionov V.S. RRC "Kurchatov Institute", Moscow, Russia
ACTIVATION METHOD FOR MEASUREMENTS PARAMETERS OF REACTOR NEUTRON SPECTRA [poster]
B.V. Efimov, A.M. Demidov, V.S. Ionov, S.I. Konjaev, S.V. Marin, V.I. Bryzgalov RRC "Kurchatov Institute", Moscow, Russia
EVALUATING NEW METHODS FOR DIRECT MEASUREMENT OF THE MODERATOR TEMPERATURE COEFFICIENT IN NUCLEAR POWER PLANTS DURING NORMAL OPERATION
M. Makai, Z. Kalya, I. Nemes, I. Pos, G. Por NPP Paks, Hungary
DETERMINING OF DISTRIBUTION BURNUP ON FUEL ASSEMBLIES AT THE REFUELING BY EMISSION TOMOGRAPHY
O.V. Maslov, M.V. Maksimov Odessa National Polytechnic University, Odessa, Ukraine
AN OPTIMAL CONTENT AND EXTENT OF THE LICENSING DOCUMENTATION FOR DUKOVANY NPP MODERNISED FUEL CYCLES
Ivan Tinka, Eva Tinkova Nuclear Research Institute Rez, division Energoprojekt, Czech Republic

HISTORY OF TIC/AER - PEOPLE AND RESEARCHES, ACHIVEMENTS AND LOST OPPORTUNITIES

TIC/AER CHRONICLE [poster]
Kravchenko Yu.Ya. RRC "Kurchatov Institute", Moscow, Russia
PAST EXPERIENCE AND WAY TO FUTURE (FROM ITC TO AER AND...)
Vladimir Lelek Nuclear Research Institute Rez, Czech Republic
BMK AND AER - IMPRESSIONS [poster]
Shishkov L.K. RRC "Kurchatov Institute", Moscow, Russia