22nd Symposium of AER on VVER Reactor Physics and Reactor Safety

Date: 2012-10-01 -- 2012-10-05

Place: Průhonice, Czech Republic

Organized by: ČEZ

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INTRODUCTION

WELCOME ADDRESS
K.Křížek ČEZ, a. s., Production Division, Czech Republic
INTRODUCTION OF ČEZ COMPANY
K.Křížek ČEZ, a. s., Production Division, Czech Republic
POST-FUKUSHIMA SAFETY REVIEWS AND SAFETY IMPROVEMENTS AT LOVIISA NPP
S.Saarinen, M.Harti, Fortum Power & Heat Ltd, Espoo, Finland
PERSONAL EXPERIENCES FROM THE POST-FUKUSHIMA TARGETED SAFETY REVIEW OF EUROPEAN NPPs
Dr. Attila Aszódi, Budapest University of Technology and Economics, Institute of Nuclear Techniques, Budapest, Hungary
SHORT SUMMARY ON PUBLICATION OF AER SCIENTIFIC PAPERS
Dr. Attila Aszódi, BUTE, Institute of Nuclear Techniques, Budapest, Hungary S. Kliem, HZDR, Institute of Safety Research, Dresden, Germany
AER ON THE INTERNET – A PROPOSAL FOR OUR ONLINE PRESENCE
Dr. Radim Vočka, František Havlůj, Nuclear Research Institute Řež (ÚJV), Czech Republic

NEW REACTOR CONCEPT

NEUTRON PHYSICAL ANALYSIS OF SIX ENERGETIC FAST REACTORS
Peter Vertes, Hungarian Academy of Sciences, Centre of Energy Research, Budapest, Hungary
THE MAIN CHARACTERISTIC OF THE EVOLUTION PROJECT SUPERVVER WITH SPECTRUM SHIFT REGULATION
P. Alekseev, V. Gorohov, P. Teplov, A. Chibiniaev, National Research Centre «Kurchatov Institute», Moscow, Russia
CALCULATIONS OF NEUTRON AND THERMO PHYSICAL CHARACTERISTICS FOR GENERATION IV REACTOR “VVER-SKD”
A.A. Pryakhin, A.V.Tikhomirov, K.Y.Kurakin, OKB “GIDROPRESS”, Podolsk, Russia

Advances in spectral and core calculation methods

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., Plzeň, Czech Republic
THE RECOVERY PROCEDURE OF PIN-BY-PIN FIELDS OF POWER DISTRIBUTION IN THE CORE OF VVER TYPE OF REACTOR FOR THE PROGRAM BIPR-8 VERIFICATION CALCULATIONS
P. Gordienko, A. Kotsarev, M. Lizorkin, National Research Centre «Kurchatov Institute», Moscow, Russia
COMPARISON OF SENSITIVITY AND UNCERTAINTY IN GD AND ER CONTAINING FUELS FOR VVER-1000 USING TSUNAMI-2D
Jan Frýbort, Czech Technical University, FNSPE, Prague, Czech Republic
HELIOS2 VERIFICATION FOR ALLEGRO CALCULATIONS STAGE 1
Radoslav ZAJAC, Petr DARILEK, VUJE, Inc., Trnava, Slovakia
EVOLUTION OF SSTC WWER CROSS SECTION LIBRARY FOR DYN3D CODE
I.Ovdiienko, M.Ieremenko,V.Khalimonchuk, A.Kuchin, SSTC N&RS, Kyiv, Ukraine
„FULLCORE“ BENCHMARK FOR VVER-440
Václav Krýsl, Pavel Mikoláš, Daniel Sprinzl, Jiří Švarný, ŠKODA JS a.s., Plzeň, Czech Republic
RESULTS OF VVER-440 BENCHMARK BY HELIOS/C-PORCA CODE
István Pós, Tamás Parkó, Paks NPP Ltd, Sándor Patai Szabó, TS-Enercon Ltd, Hungary
VALIDATION OF PIN POWER CALCULATIONS BY DYN3D ON MIDICORE AND AER KHNPP-2 BENCHMARKS
M.Ieremenko1, I.Ovdiienko1, A.Kuchin1, V.Khalimonchuk1, L.Wainer2, Ukraine
ON SOLUTION TO THE PROBLEM OF CRITICALITY
Jan Kyncl, Nuclear Research Institute Řež, plc, Czech Republic
RESULTS OF PRECISION CALCULATIONS OF THREE-DIMENSIONAL POWER DENSITY IN VVER-1000 CORE WITH FEEDBACKS USING MCU CODE
A. Bikeev, D. Shkarovsky, E. Sukhino-Khomenko, National Research Centre “Kurchatov Institute”, Moscow, Russia
THE ESTIMATION OF THE CONTROL RODS ABSORBER BURN-UP DURING THE VVER-1000 OPERATION
S. Bolshagin, S. Gorodkov, E. Sukhino-Khomenko, NRC «Kurchatov Institute», Moscow, Russia, K. Kurakin, V. Bryuhin, EDO "GIDROPRESS", Podolsk, Russia
VERIFICATION OF THE TRIGONAL GEOMETRY DIFFUSION AND SP3 MODELS OF THE CODE DYN3D
S. Duerigen,HZDR, Germany, E. Nikitin, BUTE, Institute of Nuclear Techniques, Hungary

CORE DESIGN, OPERATION AND FUEL MANAGEMENT

PREVIOUS CALCULATIONS FOR OPTIMIZATION ALGORITHMS OF NUCLEAR FUEL RELOADING AT BUDAPEST RESEARCH REACTOR
Gábor Patriskov, MTA Centre for Energy Research, H-1121 Budapest, Hungary
AER WORKING GROUP B ACTIVITIES IN 2012
Petr Dařílek, VUJE Inc., Trnava, Slovakia
FUEL CYCLES OF VVER-440
V.V. Saprykin, I.I. Yasnopolskaya, M.P. Lizorkin, А.N. Novikov, National Research Centre «Kurchatov Institute», V.A. Adeev, Kola NPP, Russia
VVER-440 FUEL ASSEMBLY ALTERNATIVES FOR HIGH BURNUP
Petr DARILEK1, Pavol CUDRNAK2, Miloš BAJAN2, Juraj TOMASKOVIC2, Slovakia
VALIDATION OF MACROCODE ANDREA FOR VVER-440 REACTORS
Lenka Heraltova, Nuclear Research Institute Řež, plc, Czech Republic
CONSOLIDATED RESULTS OF THE VVER-1000 CYCLE BURNUP CALCULATIONS BENCHMARK
TASK 1 AND TASK 2, Thomas Lötsch, TÜV SUD Industrie Service GbmH, Germany
POSSIBLE VISIBLE POWER FIELD TILTS IN BIG REACTOR CAUSED BY SMALL DEVIATIONS OF BREEDING CAPABILITIES OF FUEL ASSEMBLIES
E.Mikailov, A.Sumarokova, L.Shishkov, National Research Centre “Kurchatov Institute”, Moscow, Russia
USE OF ERBIUM AS BURNABLE POISON FOR VVER
A. Pavlovichev, E. Kosourov, Anastasia Shcherenko, V. Saprykin, A. Lazarenko, S. Aleshin, Anna Shcherenko, National Research Center «Kurchatov Institute», Moscow, Russia
AUTOMATIC LOADING PATTERN OPTIMIZATION TOOL FOR LOVIISA VVER-440 REACTORS
Jaakko Kuopanportti, Fortum Power and Heat ltd, Espoo, Finland
OPTIMIZATION FEASIBILITY STUDY ON DUKOVANY VVER-440 LONG FUEL CYCLES WITH INNOVATIVE FUEL TYPES
J.Prehradný, K.Katovský, ŠKODA JS, a.s., R.Čada, FAS UWB, Pilsen, T.Kurka, FNSPE CTU in Prague, Czech Republic

CORE MONITORING, SURVEILLANCE AND TESTING

PROPOSAL OF THE IONIZATION CHAMBERS READINGS CORRECTION FOR THE UNDERCRITICALITY EVALUATION DURING CRITICALITY REACHING
J.Bajgl, Dukovany NPP, Czech Republic
AER WORKING GROUP C ACTIVITY IN 2012
Imre Nemes, Paks NPP Ltd, Hungary
EXPERIENCES WITH APPLICATION OF GD-2N ASSEMBLIES IN PAKS NPP
Imre Nemes, Tamás Parkó, Paks NPP Ltd, Hungary
COMPARISON OF CALCULATED AND VERIFIED DATA ON CORE POWER DENSITY DISTRIBUTION AT DUKOVANY NPP
E. Mikailov, E. Solovieva, L. Shishkov, National Research Centre «Kurchatov Institute», Moscow, Russia, J. Bajgl, Dukovany NPP, Czech Republic
VERETINA – A COUPLED NEUTRON PHYSICS AND THERMAL-HYDRAULIC CODE FOR PERFORMING DETAILED ANALYSIS OF TRANSIENT PROCESSES IN VVER-440 REACTORS
István Pós(1), Zoltán Kálya(1), Gábor Házi(2), József Páles(2), Csaba Horváth(2), János Végh(2), Hungary
SCORPIO-VVER CORE SURVEILLANCE SYSTEM FOR VVER-440 REACTORS IN CZECH REPUBLIC AND SLOVAK REPUBLIC
Jozef Molnár, Nuclear Research Institute Řež plc, Czech Republic
METHOD OF ACCURATE DETERMINATION OF VVER-440 REACTOR THERMAL POWER APPLYING EX-CORE DETECTOR SIGNALS
István Pós, Tamás Parkó, Zoltán Kálya, Paks NPP Ltd
PRIMARY SYSTEM HYDRAULIC CHARACTERISTICS AFTER MODIFICATION OF REACTOR COOLANT PUMPS` IMPELLER WHEELS AT BOHUNICE NPP
Martin Závodský, Jozef Hermanský, VUJE Inc., Okružná 5, 918 64 Trnava, Slovakia
DETERMINATION OF THERMAL COEFICIENTS OF REACTIVITY FOR NPP MOCHOVCE-3
4 START-UP CONDITIONS USING MCNP5, G.Farkas1, J.Lüley1, B.Vrban1, J.Haščík1, M.Petriska1, R.Hinca1, V.Slugeň1, J.Šimko2, Slovakia
CONTROL OF ABSORBING ELEMENT LIFETIME DURING OPERATION OF VVER 1000
K.Y.Kurakin, S.A.Kushmanov, V.V.Bryukhin, OKB “GIDROPRESS”, Russia

ENGINEERING FACTORS

AER WORKING GROUP H ACTIVITY IN 2012
L. Shishkov, E.Mikailov, National Research Centre «Kurchatov Institute», Moscow, Russia
THE METHODOLOGICAL COMPONENTS OF THE ENGINEERING FACTORS AND THEIR ALTERNATIVE DETERMINATION
J.Švarný, ŠKODA JS a.s., Plzeň, Czech Republic
CONTRIBUTION OF THE NUMBER OF MEASURED DATA TO CALCULATION UNCERTAINTY IN THE WORTH OF VVER CONTROL RODS
A. Sumarokova, L. Shishkov, National Research Centre “Kurchatov Institute”, Moscow, Russia
MET. ΣQ CALCULATION USING MEASURED AND CALCULATED TEMPERATURE RISES
Martin Šašek, ŠKODA JS a.s, Plzeň, Czech Republic
UNCERTAINTIES OF THE NEUTRONIC CALCULATIONS AT CORE LEVEL DETERMINED BY THE KARATE CODE SYSTEM AND THE KIKO3D CODE
István Panka, András Keresztúri, Centre for Energy Research, Hungarian Academy of Sciences, Reactor Analysis Department, Budapest, Hungary (prez.G.Hegyi)
CALCULATION OF MINIMUM DNBR IN NUCLEAR REACTOR CORE BASED ON STATISTICAL MODELS NEUTRON - PHYSICAL AND THERMOHYDRAULIC PROCESSES
A. Ryzhov, D. Oleksyuk, A. Pinegin, National Research Centre “Kurchatov Institute”, Moscow, Russia

CRITICALITY SAFETY

WG E activities in 2012
Vladimír Chrapčiak, VUJE, Inc., Slovakia
VERIFICATION SCALE 6 AND HELIOS FOR NUCLIDE COMPOSITION CALCULATION
Vladimír Chrapčiak, Radoslav Zajac, VUJE, Inc., Slovakia
SCALE6 VALIDATION AGAINST VVER-440 EXPERIMENTAL DATA
Nikolay Mihaylov, Maria Manolova, INRNE-BAS, Sofia, Bulgaria
CRITICALITY CALCULATION FOR POOLS AT REACTOR IN SLOVAKIA
Vladimír Chrapčiak, Radoslav Zajac, Branislav Hatala, VUJE, Inc., Slovakia

NEUTRON KINETICS AND REACTOR DYNAMICS METHODS

POST TEST CALCULATIONS OF A SEVERE ACCIDENT EXPERIMENT FOR VVER-440 REACTORS BY THE ATHLET CODE
H. György(1), I. Trosztel(2) , (1)Budapest University of Technology and Economics, Institute of Nuclear Techniques, (2)Hungarian Academy of Sciences, Centre for Energy Research
THE FIRST COMPARISON OF THE SEVENTH AER DYNAMIC BENCHMARK PROBLEM RESULTS OBTAINED BY RELAP5-3D AND DYN3D/ATHLET COMPUTING CODES
Marek Benčík, Jan Hádek*), Yaroslav Kozmenkov**), Sören Kliem**), *)NRI, Czech Republic, **)HZDR, Germany
CALCULATION OF THE SECOND KINETIC AER BENCHAMRK BY USING NEW NODAL METHODS
I. Pataki, A.Keresztúri, Centre for Energy Research, Hungarian Academy of Sciences, Reactor Analysis Department, Budapest, Hungary
FROM MACRO- TO MICROSCALE HYDRAULIC SIMULATIONS OF A REACTOR PRESSURE VESSEL IN THE FRAMEWORK OF THE SYSTEM CODE ATHLET
Nikonov S.P., NRC “Kurchatov Institute”, Moscow, Russia, I. Pasichnyk, K. Velkov, GRS mbH, Garching, Germany
APPLICATION OF THE METHOD FOR UNCERTAINTY AND SENSITIVITY EVALUATION TO RESULTS OF PWR LBLOCA ANALYSIS CALCULATED WITH THE CODE ATHLET
U. Rohde, Y. Kozmenkov, Helmholtz-Zentrum Dresden-Rossendorf, Institute of Resource Ecology, P.O.B. 51 01 19, D-01314 Dresden, Germany
COMPARISON OF HFP STATE RESULTS FOR KALININ-3 BENCHMARK CALCULATED WITH THE CODES BIPR8 AND DYN3D
P. Gordienko*), A. Kotsarev*), M. Lisorkin*), Yaroslav Kozmenkov**), S. Kliem**), *) KI, Russia, **) HZDR, Germany
SIMULATION OF THE OECD/NEA ’KALININ-3’ BENCHMARK(PHASE-2) BY THE KIKO3D AND ATHLET CODES
András Keresztúri, István Trosztel, Zsolt Elter, György Hegyi, Centre for Energy Research, Hungarian Academy of Sciences, Reactor Analysis Department, Budapest, Hungary
ATHLET BASED TRAINING OF NEURAL NETWORKS FOR THE ANALYSIS OF NUCLEAR POWER PLANT (NPP) SAFETY
Katkovsky Е.А., Katkovsky S.E, “Energoautomatika” Ltd, Moscow, Russia, Nikonov S.P., NRC “Kurchatov Institute”, Moscow, Russia, I. Pasichnyk, K. Velkov, T. Voggenberger, GRS mbH, Garching, Germany
THE THERMOMECHANICAL MODEL USED IN THE MODULE OF CODE ATHLET\BIPR-VVER FOR A QUANTITY ESTIMATION FAILURED FUEL RODS IN ACCIDENTS RIA
V. Proselkov, A. Kotsarev, M. Lizorkin, National Research Centre “Kurchatov Institute”, Moscow, Russia
CHARACTERIZATION OF A REPRESENTATIVE VVER-440 FUEL ROD WITH THE STATISTICAL ENIGMA
Elina Syrjälahti, VTT Technical Research Centre of Finland
VALIDATION OF DYN3D PIN-POWER CALCULATION AGAINST EXPERIMENTAL RESULTS FROM THE LR-0 REACTOR
Jan Hádek, ÚJV Řež, a.s., Czech Republic

CFD CODES APPLICATION

AER WORKING GROUP H ACTIVITIES IN 2012
Dr. Attila ASZÓDI, Budapest University of Technology and Economics, Institute of Nuclear Techniques, Hungary
THERMO-HYDRAULIC ANALYSIS OF FUEL ASSEMBLY OF NUCLEAR REACTOR VVER 440
V.Kutiš, E.Mojto, J.Jakubec, J.Paulech, Slovak University of Technology, FEEIT, Bratislava, Slovakia
CFD ANALYSIS OF TEMPERATURE DEVIATIONS IN GD ASSEMBLY HEADS
S. Tóth, A. Aszódi, Budapest University of Technology and Economics, Institute of Nuclear Techniques, Hungary