23rd Symposium of AER on VVER Reactor Physics and Reactor Safety

Date: 2013-10-30 -- 2013-11-04

Place: Štrbské Pleso, Slovakia

Organized by: VUJE / SE / UJD

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Opening of the Symposium

Opening of the Symposium
K. Rovný, VUJE
Welcome address
E. Ďurček, SE
Welcome address
P. Uhrík, UJD SR

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., Czech Republic
DEVELOPMENT OF A TRANSPORT SOLVER FOR DYN3D ON THE BASIS OF CCCP WITH ORTHONORMAL FLUX EXPANSION
Dzianis Litskevich, Bruno Merk, Helmhotz-Zentrum Dresden-Rossendorf, Germany
DEVELOPMENT AND VERIFICATION NEW NODAL METHODS IN THE KIKO3DMG CODE
István Pataki, András Keresztúri, MTA EK, Hungary
ON SOLUTION TO THE PROBLEM OF REACTOR KINETICS WITH DELAYED NEUTRONS BY MONTE CARLO METHOD
Jan Kyncl, UJV Řež, Czech Republic
ANDREA 2 - improved version of core physics code for VVER reactors
F. Havlůj, R. Vočka, ÚJV Řež, Czech Republic
DEVELOPMENT OF APPROXIMATION METHOD TO EVALUATE ISOTOPIC COMPOSITION OF DEPLETED FUEL, S .Aleshin, A. Shcherenko,
National Research Centre “Kurchatov Institute”, Russia
DEFINITION OF MESH POINTS FOR PREPARATION OF TABLE FORM CROSS-SECTION LIBRARY FOR DYN3D CODE
A.Kuchyn, I.Ovdiienko, State Scientific and Technical Centre on Nuclear and Radiation Safety, Kyiv, Ukraine
EFFECT OF FUEL BURNUP HISTORY ON NEUTRON-PHYSICAL CHARACTERISTICS OF WWER-1000 CORE
I.Ovdiienko1, I.Bilodid2, M.Ieremenko1, V.Khalimonchuk1, A.Kuchin1, 1 State Scientific and Technical Centre on Nuclear and Radiation Safety, Kyiv, Ukraine, 2 HZDR, Dresden, Germany
COMPARISON OF FINITE DIFFERENCE AND NODAL MOBY-DICK MACROCODE CALCULATIONS
M.Šašek1, R. Kužel2, V. Krýsl1, 1 ŠKODA JS a.s., 2 Department of Mathematics, University of West Bohemia, Czech Republic
The ENGINEERING FACTORS OF THE MACROCODE MOBY-DICK, J.
Švarný, M. Šašek, S. Štech, ŠKODA JS a.s., Czech Republic
DEVELOPMENT OF GRAPHIC SHELL AND DATABASE TO SUPPLY CODE KASKAD WITH CONSTANTS
S. Aleshin, I. Gazhur, National Research Centre “Kurchatov Institute”, Russia

Reactor physics experiments and code validation (benchmarks)

NUMERICAL-EXPERIMENTAL RECOVERY OF POWER DENSITY IN VVER CORE BASED ON MAXIMUM LIKELIHOOD ESTIMATION AND EVALUATION OF ITS QUALITY BY FULL-SCALE VVER-MCU MODEL
S. Gorodkov, National Research Centre “Kurchatov Institute”, Russia
Verification of code TDMCC for the nuclear safety analysis problems FOR VVER-type NPP fuel SUBSTANTIATION
Tikhomirov A.V., Antonov S.N., Pryakhin A.A., Kurakin K.Yu., OKB "GIDROPRESS", Russia
Precise Geometry Solution of Full Core Benchmark by HELIOS2 Spectral Code
Petr DARILEK, Radoslav ZAJAC, VUJE, Inc., Slovakia
SOLUTION OF THE ‘FULL-CORE’ VVER-440 CALCULATION BENCHMARK BY KARATE: ANALYSIS AND CONCLUSIONS
E.Temesvári, G.Hordósy, Gy.Hegyi, A. Keresztúri, Cs.Maráczy, Hungarian Academy of Sciences, Hungary
„FULL CORE“ BENCHMARK FOR VVER-440
Václav Krýsl, Pavel Mikoláš, Daniel Sprinzl, Jiří Švarný, ŠKODA JS a.s., Czech Republic
THE DYN3D TRIGONAL-GEOMETRY DIFFUSION MODEL – VERIFICATION USING THE AER-FCM-101 BENCHMARK
S. Duerigen, S. Kliem, Institute of Resource Ecology, Rossendorf, Germany
ASSURANCE BY EXPERIMENTS OF CALCULATION METHODS FOR POWER DISTRIBUTION IN VVER FUEL GRIDS IN CASE OF WATER GAP VARIATION BETWEEN FUEL ASSEMBLIES
N. Alekseev, Yu. Kravchenko, Yu. Krainov, S. Marin, L. Shishkov, National Research Centre “Kurchatov Institute”, Russia
STATISTICAL MODEL OF POWER DISTRIBUTION ABOUT VVER-1000 REACTOR CORE, AND THE MODEL APPLICATION IN THE ANALYSIS OF POWER FIELD DISTRIBUTIONS IN FUEL CYCLES
A. Pinegin, National Research Centre “Kurchatov Institute”, Russia
Benchmark Calculations with the Monte Carlo Reactor Physics Burnup Code SERPENT for Fuel Assemblies of VVER-440 and VVER-1000 types
Lötsch Thomas, TUV SUD Industrie Service GmbH, Münich, Germany
Consolidated Data for the Task 2 of the VVER-1000 Core Burnup Benchmark
Lötsch Thomas, TUV SUD Industrie Service GmbH, Münich, Germany

Fuel management issues

AER WORKING GROUP B ACTIVITIES IN 2013
Petr DARILEK, VUJE, Inc., Slovakia
CORE DESIGN AT PAKS NPP USING NEURAL NETWORKS
Gábor BÓNA, Paks NPP Hungary
PIN BURN-UP OPTIMIZATION at Dukovany NPP
Martin Bárta, Josef Bajgl, CEZ Inc., Dukovany NPP, Czech Republic
Highly Enriched Alternatives of VVER-440 Fuel Assembly
Miloš BAJAN1, Petr DARILEK2, 1Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, 2VUJE, Inc., Slovakia
PRINCIPAL RESULTS OF EXPERIMENTAL-COMMERCIAL OPERATION OF VVER-440 FUEL OF 3-D GENERATION, V. Saprykin, I. Yasnopolskaya, A.
Gagarinskiy - National Research Centre “Kurchatov Institute”, V. Adeev - Kola NPP, Russia
Paks NPP status and transient to 15 m cycles
Imre NEMES, MVM Paks NPP Ltd.,Hungary
Experience with Gd-fuel Implementation at Dukovany NPP
Josef Bajgl, Martin Bárta, CEZ Inc., Dukovany NPP, Czech Republic

Core surveillance and monitoring

AER WORKING GROUPS C&G ACTIVITY IN 2013
Imre Nemes,Paks NPP Ltd, Hungary
COMPARISON ANALYSIS OF DIAGNOSTIC METHODS OF COOLANT LOCAL BOILING IN VVER CORE FOR EFFECTIVENESS
Yu. Semchenkov, V. Milto, D. Vorobiova, B. Shumskiy, National Research Centre “Kurchatov Institute”, Russia
The SCORPIO-VVER Core monitoring and Surveillance System with Enhanced Capabilities
Jozef Molnar, ÚJV Řež, Czech Republic
Acoustic monitoring methods applied in nuclear power plants
G. Por, Institute of Nuclear Technique, Technical University of Budapest Hungary
Primary system hydraulic characteristics after modification of reactor coolant pumps` impeller wheels at Bohunice NPP executed in 2013
Martin Závodský, Jozef Hermanský, Division for Preparation of NPP Operation, VUJE Inc., Okružná 5, 918 64 Trnava, Slovakia
FORMATION OF ASYMPTOTIC SPECTRUM IN SUBCRITICAL VVER REACTORS
L. Shishkov, M. Zizin, National Research Centre “Kurchatov Institute”, Russia

Reactor dynamics and safety analysis

AER WORKING GROUP D ON VVER SAFETY ANALYSIS – REPORT OF THE 2013 MEETING
S. Kliem, Institute of Resource Ecology Rossendorf, Germany
RESULTS OF TEST CALCULATION OF VVER REACTIVITY ACCIDENTS OBTAINED BY PIN-BY-PIN POWER FIELD RECOVERY MODULE BUILT IN, AS A PART OF PROGRAM COMPLEX ATHLET / BIPR-VVER
P. Gordienko, A. Kotsarev, M. Lizorkin, National Research Centre “Kurchatov Institute”, Russia
EVALUATION OF EMERGENCY PROTECTION EFFECTIVENESS ON THE BASIS OF MEASURED WORTH OF CERTAIN CR GROUPS
D. Afanasiev, A. Pinegin, National Research Centre “Kurchatov Institute”, Russia
INVESTIGATION OF THE HOT CHANNEL CALCULATION METHODOLOGY IN CASE OF SHROUD-LESS ASSEMBLIES
Á Tóta, A. Keresztúri, A. Molnár, I. Panka, , Hungarian Academy of Sciences, Hungaria
ANALYSIS OF INFLUENCE OF THE UNCERTAINTIES AVAILABLE WHEN PREPARING THE SMALL-GROUP CONSTANTS ON THE VVER NEUTRONIC CHARACTERISTICS
V.V. BRYUKHIN, M.A. UVAKIN, K.YU. KURAKIN, OKB "GIDROPRESS"
Assessment of the uncertainties of COBRA sub-channel calculations by using a PWR type rod bundle and the OECD NEA UAM and PSBT benchmarks data
István Panka, András Keresztúri, Centre for Energy Research, Hungarian Academy of Sciences, Hungary
SENSITIVITY ANALYSIS ON THE RANKING OF INPUT UNCERTAINTIES WITH RESPECT TO PEAK CLADDING TEMPERATURE UNCERTAINTY IN A PWR LBLOCA ANALYSIS
U. Rohde, Y. Kozmenkov, Helmholtz-Zentrum Dresden-Rossendorf, Institute of Resource Ecology, Germany
LOWERING ENGINEERING FACTOR FOR DNBR MARGIN FOR FUEL ASSEMBLIES TVS-2M AND TVSA
D. Oleksuk, A. Pinegin, A. Ryzhov, National Research Centre “Kurchatov Institute”, Russia
Calculation study of the Novovoronezh NPP power unit No. 5 reactor VVER-1000 dynamic stability at the boron control malfunction caused by the pure condensate inflow into the primary coolant circuit
Vytkovsky I. - Novovoronezh NPP, Nikonov S. - National Research Center „Kurchatov Institute“, Ryasnyy S. - JSC «ATOMTECHENERGO», Russia
SENSITIVITY OF HYDRODYNAMIC PARAMETERS’ DISTRIBUTIONS IN VVER-1000 REACTOR PRESURE VESSEL (RPV) WITH RESPECT TO UNCERTAINTY OF THE LOCAL HYDRAULIC RESISTANCE COEFFICIENTS
I. Pasichnyk1, S. Nikonov2, K. Velkov1, 1Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Germany 2NRC „Kurchatov Institute“, Russia
APPLICATION OF NEURAL NETWORKS FOR THE ANALYSIS OF VVER-1000 REACTOR PRESSURE VESSEL HYDRODYNAMICS
Katkovsky Е.А.1, Katkovsky S.E.1, S. Nikonov2, I. Pasichnyk3, K. Velkov3, 1“Energoautomatika” Ltd, Moscow, Russia, 2NRC „Kurchatov Institute“, Russia, 3Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Garching, Germany
Analysis Compare of Uncontrolled Withdrawal of Control Rods Group at a Certain Power of VVER and M310
WANG Yanping, ZHAO Yang, DU Sijia, National Key Laboratory of Science and Technology on Reactor System Design Technology, Nuclear Power Institute of China
Experience with DYN3D for safety analyses of VVER440 reactors
Ctibor STRMENSKÝ, VUJE, Inc., Slovakia

Nuclear applications of computational fluid dynamics (CFD)

Determination of the critical submergence at pump intakes in NPP with a new approach combining ANSYS CFX with the analytical vortex model of Burgers &
Rott, P. Pandazis, F. Blömeling, TŰV NORD SysTec GmbH, Germany
CFD investigation of flow in the MATIS-H test facility
L. Tiborcz, S. Tóth, A. Aszódi, Budapest University of Technology and Economics, Hungary
Experimental investigation of the MSFR molten salt reactor concept
Yamaji Bogdán, BME Institute of Nuclear Techniques Budapest, Hungary

Fuel behaviour in normal conditions

INVESTIGATIONS OF AXIAL DISTRIBUTION OF TVEL SIMULATOR TEMPERATURE PERFORMED AT A 37-ROD FA MODEL OF REACTOR VVER-100
L. Kobzar, D. Oleksuk, V. Bugaeva, D. Kireeva, National Research Centre “Kurchatov Institute”, Moscow, Russia

Spent fuel storage and disposal

AER Working Group E in 2013
Vladimír Chrapčiak, VUJE, Inc., Slovakia
A solution of CB6 benchmark on VVER-440 final disposal with Monte Carlo reactor physics code Serpent
Tuukka Lahtinen, Fortum Power and Heat Ltd, Finland
COMMENT OF RESULTS OF BENCHMARK BASED ON #3958 ISTC PIE SOLVED BY WIMS CODE
Pavel Mikoláš, ŠKODA JS a.s., Czech Republic
Methodologies for determination activation of steel components and concrete structures of WWER-440 type nuclear power plants
Boglárka Babcsány, Physics MSc.; Szabolcs Czifrus, Dr., BME NTI; Sándor Fehér, Dr., BME NTI, Budapest University of Technology and Economics, Hungary
SCALE 6.1.2 - some comments to possible models of assembly for criticality and inventory calculation
V. Chrapčiak, VUJE, Slovakia
MULTIGROUP ENERGY STRUCTURE FOR BA FUEL DEPLETION ANALYSIS
M. Lovecký, 1ŠKODA JS a.s., Czech Republic
RADIONUCLIDE INVENTORY CALCULATIONS IN VVER-440 REACTOR COMPONENTS
Amine Bouhaddane, Gabriel Farkas, Vladimír Slugeň, Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Institute of Nuclear and Physical Engineering

Innovative technologies and methods

Information about AER WG F
Lev Shishkov, National Research Centre “Kurchatov Institute”, Russia
HPLWR FINE MESH CORE ANALYSIS
E. Temesvári, Gy. Hegyi, G. Hordósy, Cs. Maráczy, A. Molnár, Hungarian Academy of Sciences, Hungary
ALLIANCE for ALLEGRO
Petr DARILEK, VUJE, Inc., Slovakia
DEVELOPMENT OF DYNAMIC MEANS FOR TECHNNOLOGICAL AND ECONOMIC ANALYSIS AND PERFORMANCE THE MANAGEMENT OF NETWORK SYSTEM OF CLOSED FUEL CYCLE IN NUCLEAR POWER INDUSTRY
A. Ignatov, S. Subbotin, P. Alekseev, National Research Centre “Kurchatov Institute”, Russia