24th Symposium of AER on VVER Reactor Physics and Reactor Safety

Date: 2014-10-14 -- 2014-10-18

Place: Sochi, Russia

Organized by: KI / TVEL / GIDROPRESS / VNIIAES

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Opening of the Symposium

LESSONS LEARNED FROM ACCIDENTS IN NUCLEAR INDUSTRY
Prof. V.ASMOLOV, First Deputy Director General Rosenergoatom Concern OJSC, Moscow, Russia
SCIENTIFIC PROGRAM OF NRC “KURCHATOV INSTITUTE” IN THE AREA OF NUCLEAR TECHNOLOGIES
Ya.I.Shtrombakh, Moscow, Russia
SUSTAINABLE NUCLEAR ENERGY STRATEGY AND NEW DESIGNS: RUSSIAN APPROACH
A.Yu.Gagarinskiy, National Research Centre “Kurchatov Institute”, Moscow, Russia

Fuel management issues

NUCLEAR FUEL FOR NPPs WITH VVER: STATUS AND PERSPECTIVE DESIGN
Dolgov A.B., Kukushkin Y.A., Ugryumov A.V., JSC “TVEL”, Moscow, Russia
DIFFERENT FUEL OPTIONS FOR THE 15-MONTH CYCLES OF PAKS NPP UNITS
Imre Nemes1), Istvan Pos1), Sandor Patai szabo2), 1) Paksh NPP Ltd, 2) TS Enercom Ltd., Hungary
VVER-1000 FUEL CYCLES: CURRENT SITUATION AND PERSPECTIVE
Volkov E.S., Kosourov E.K., Pavlov V.I., Pavlovichev A.M., Spirkin E.I, Shcherenko Anastasia I., NRC “Kurchatov Institute”, Moscow, Russia
NEW FUEL CYCLE STRATEGIES FOR VVER-440
Gagarinskiy А.А., Ivanova E.G., Lizorkin M.P., Proselkov V.N., NRC “Kurchatov Institute”, Moscow, 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
Mikolas Pavel, SKODA JS a.s., Czech Republic, Petr Darilek, VUJE Inc., Slovakia.
AER WORKING GROUP B ACTIVITIES IN 2014
Petr Darilek, VUJE Inc., Slovakia
DEVELOPMENT OF CODES AND «KASKAD» COMPLEX
Lizorkin M.P., NRC «Kurchatov institute», Moscow, Russia
DEVELOPMENT OF METHODICAL APPROACHES IN VVER CALCULATIONS
Bolobov P.A., Lazarenko A.P., Tomilov M.Ju., NRC «Kurchatov institute», Moscow, Russia
ACCOUNTING FOR IMPACT OF FA GAP DEVIATIONS IN VVER-1000 TO ENGINEERING MARGIN FACTORS
Shishkov L.K, Gorodkov S.S., Mikailov E.F., Sukhino-Homenko E.A, Sumarokova A.S,. NRC «Kurchatov Institute», Moscow, Russia
ASSESSMENT OF THE UNCERTAINTIES OF MULTICELL CALCULATIONS BY THE OECD NEA UAM PWR PIN CELL BURNUP BENCHMARK
Istvan Panka, Andras Kereszturi, Centre for Energy Reserch, Hungary
INVESTIGATION OF EFFECT PRODUCED BY FLUID TRANSVERSE FLOWS BETWEEN VVER FUEL ASSEMBLIES TO CONSERVATISM OF THERMAL-HYDRAULIC ANALYSIS IN A CONSISTENT SOLUTION OF NEUTRONIC AND THERMAL-HYDRAULIC TASKS
Shumskiy B.E, Kotsarev A.V., Lizorkin M.P., NRC “Kurchatov Institute”, Moscow, Russia
3-D SIMULATION OF VVER CORE POWER DENSITY BASED ON SAPFIR_95&RC_VVER ALGORITHMS
Artemov V.G., Kuznetsov A.N., Shemaev Yu. P., FSUE «Alexandrov NITI», Russia
CALCULATION OF NEUTRON AND GAMMA-RAY DOSE RATES BY THE USE OF THE MONTE CARLO CODE MCU
Oleynik D.S. NRC “Kurchatov institute”, Moscow, Russia
JUSTIFICATION OF PROPER DEGREE OF CONSERVATISM IN CALCULATION OF ENGINEERING MARGIN FACTORS FOR DNBR AS APPLIED TO VVER-1000 CORES CONTAINING FUEL ASSEMBLIES OF VARIOUS TYPES
Oleksyuk D., Pinegin A., Ryzhov A., NRC “Kurchatov Institute”, Moscow, Russia
METHODOLOGY OF 3D NEUTRON-PHYSICAL CALCULATION OF NUCLEAR REACTORS OF AXIAL-SYMMETRY WITH FINITE STEP ALONG THE AXIS
Poveschenko T.S., Laletin N.I., Sultanov N.V., NRC «Kurchatov institute», Moscow, Russia
METHODOLOGY OF CALCULATING THE AXIAL LEAKAGE FOR NUCLEAR REACTORS OF AXIAL SYMMETRY
Poveschenko T.S., Laletin N.I., NRC «Kurchatov institute», Moscow, Russia
AVOIDING A TWICE ACCOUNTING OF MACRO-COMPONENT IN THE UNCERTAINTY OF ESTIMATED ENGINEERING MARGIN FACTORS FOR PARAMETERS OF VVER POWER DENSITY
Dementiev V.G., Gorodkov S.S., Mikailov E.F., Shishkov L.K., Sukhino-Homenko E.A., Sumarokova A.S., NRC “Kurchatov Institute”, Moscow, Russia
FULL-CORE' VVER-440 BENCHMARK EXTENSION
Václav Krýsl, Pavel Mikoláš, Daniel Sprinzl, Jiří Švarný, ŠKODA JS a. s., ŠKODA JS

Reactor physics calculations, experiments and code validation

VERIFICATION OF SAPFIR_95&RC_VVER PACKAGE FOR CORE NEUTRONIC CALCULATIONS IN EXTENDED RANGE OF PERMISSIBLE VALUES OF VVER PARAMETERS
Artemov V.G., Artemova L.M., Zinatullin R.E., Ivanov A.S., Kuznetsov A.N., Piskarev A.V., Shemaev Yu. P., FSUE «Alexandrov NITI», Russia; Kurakin K.Yu., Tihomirov A.N., Fateyev M.B., OKB «GIDROPRESS», Russia
APPLYING FULL SETS OF MULTIGROUP CELL CHARACTERISTICS OBTAINED BY MCU CODE IN FINITE-DIFFERENCE CALCULATIONS OF VVER NEUTRON FIELD
Gorodkov S.S., Kalugin M.A, NRC “Kurchatov institute”, Russia
EXPERIENCE WITH VVER-440 FUEL OF THE 2-ND GENERATION WITH GD (AVERAGE ENRICHMENT 4.87 %) AT SLOVAK NPP SITES
Sedlacek M.1), Chrapciak V.1), Simko J.2), Grezd’o O.3), 1) VUJE Inc., Slovakia, 2) SE Inc. – Enel, Mochovce NPP Slovakia, 3) SE Inc. – Enel, Bohunice NPP Slovakia.
CALCULATIONS OF 3D FULL-SCALE FA MODELS WITH FEEDBACKS AND BURNUP USING MCU AND BIPR-7A CODES
Aleshin S.S., Bikeev A.S., Kalugin M.A., Kosourov E.K., Pavlovichev A.M., Sukhino-Khomenko E.A., Shcherenko Anna I., Shkarovskiy D.A., NRC «Kurchatov institute», Russia
3D CALCULATIONS (WITHOUT FEEDBACK) OF EQUILIBRIUM VVER- 1000 FUEL CYCLE WITH THE REALISTIC BURNUP DISTRIBUTION IN CORE USING MCU AND BIPR-7A CODES
Bolshagin S.N., Kosourov E.K., Pavlovichev A.M., Prjanichnikov A.V., Shcherenko Anastasia I., NRC “Kurchatov Institute”, Russia
OUTCOMES OF CALCULATING CRITICAL ASSEMBLIES OF RIG ZR-6 USING SPECTRAL CODE TVS-M
Tsvetkov V.M., NRC “Kurchatov Institute”, Russia
ANALYSIS OF APPLICATION OF VARIOUS VERSIONS OF FUEL ROD AXIAL PROFILING IN VVER-1000 USING THE SOFTWARE SAPFIR_95&RC
Zuev A.A., Ustinov A.N., Fateev M.V., Kurakin K.Yu., OKB «Gidropress», Russia
USAGE OF BURNT FUEL ISOTOPIC COMPOSITIONS, OBTAINED BY ENGINEERING CODES, IN MONTE-CARLO CODE CALCULATIONS
Aleshin S.S., Gorodkov S.S., Shcherenko A.I., NRC “Kurchatov institute”, Moscow, Russia

Core surveillance and monitoring

ACTIVITIES AER WORKING GROUP C IN 2014
I. Nemes, NPP Paks, Hungary
VVER OPERATION CONTROL MEASUREMENTS
Kalinushkin A.E., Milto N.V., Semchenkov Yu.M., NRC «Kurchatov Insitute», Moscow, Russia
THE SCORPIO-VVER CORE MONITORING AND SURVEILLANCE SYSTEM FOR VVER-440 TYPE OF REACTORS
Josef Molnar, UJV Res, a. s., Czech Republic.
EVALUATION OF EXPERIMENTAL UNCERTAINTY OF PHYSICAL MEASUREMENTS BASED ON START-UP DATA OF THE LATEST VVER-1000 PLANTS
Tsyganov S., Kravchenko A., Kraynov Yu., Nasedkin A., Chmykhun V., NRC «Kurchatov institute», Moscow, Russia
EXPERIMENTAL AND COMPUTATIONAL INVESTIGATIONS OF HEAT MASS TRANSFER INTENSIFIER GRIDS OF VARIOUS DESIGNS FOR EFFECTIVENESS
Kobzar L.L., Oleksyuk D.A., Semchenkov Y.M., NRC «Kurchatov institute», Russia
FINAL RESULTS OF THE PRIMARY SYSTEM HYDRAULIC CHARACTERISTICS AFTER MODIFICATION OF REACTOR COOLANT PUMPS IMPELLER WHEELS AT BOHUNICE NPP EXECUTED BETWEEN 2012-2014
Martin Zavodsky, Josef Hermansky, Vuje Inc., Slovakia
ANALYSIS OF THE REASONS FOR ABNORMAL READINGS OF TCS AT THE MOCHOVCE NPP UNITS
Kuzil А.S., Padun S.P., Surnatchev S.I., NRC "Kurchatov Institute", Moskow, Russia
NUMERICAL AND EXPERIMENTAL INVESTIGATION OF 3D COOLANT TEMPERATURE DISTRIBUTION IN THE HOT LEGS OF PRIMARY CIRCUIT OF REACTOR PLANT WITH WWER-1000
Saunin Yu., Dobrotvorski A., Semenikhin A., Ryasny S., JSC «ATOMTECHENERGO», Russia
THE PRACTICE OF CONSIDERING REACTIVITY SPATIAL EFFECTS WHEN MEASURING EMERGRNCY PROTECTION EFFICIENCY IN VVER REACTORS
Afanasiev D.V., Pinegin A.A. NRC “Kurchatov Institute”, Moscow, Russia; Orlov V.I., Tolmasova E.V. VNIIAES, Moscow, Russia.
PROCESSES OF ERROR DETECTION IN THE PATTERN OF CORE LOADING, COMMUTATION OF NITC AND MISALIGNMENT IN CONTROL ROD POSITION IN VVER-TOI REACTOR USING THE THEORY OF PATTERN RECOGNITION
Pinegin A. , Ryzhov A., NRC “Kurchatov Institute”, Moscow, Russia
AN ANALYSIS OF REACTIVITY PREDICTION DURING THE REACTOR START-UP PROCESS
Josef Bajgl, CEZ Inc., Dukovany NPP Czech Republic, Václav Krýsl, Jiří Švarný, ŠKODA JS, a.s ŠKODA JS a. s.
COMPARISON OF THE ACCURACY OF DIFFERENT METHODS OF MEASURING THE EFFECTIVENESS OF EMERGENCY PROTECTION SYSTEM IN VVER-1000
Afanasiev D.A., Pinegin A.A., NRC “Kurchatov institute”, Moscow, Russia

Reactor dynamics and safety analysis

AER WORKING GROUP D ON VVER SAFETY ANALYSIS – REPORT OF THE 2014 MEETING
S. Kliem, Helmholtz-Zentrum Drezden-Rossendorf, Institute of Resource Ecology, Germany
EXPERIENCES WITH DYN3D FOR SAFETY ANALYSES OF VVER-440 REACTORS
Ctibor Strmensky, VUJE Inc., Slovakia
COMPARISON OF THE RESULTS OF THE 7th DYNAMIC AER BENCHMARK – VVER-440 PRESSURE VESSEL COOLANT MIXING BY RE- CONNECTION OF AN ISOLATED LOOP
Kotsarev A.V., Lizorkin M.P., NRC «Kurchatov Institute», Moscow, Russia
ANALYSIS OF CORE BEHAVIOR UNDER SEVERE ACCIDENTS USING SOCRAT/B1 CODE
Lityshev A., Pantyushin S., Aulova O., Gasparov D., Bukin N., Bykov M., OKB «GIDROPRESS», Russia
NEUTRON-KINETIC AND THERMO-HYDRAULIC UNCERTAINTIES IN THE STUDY OF KALININ-3 BENCHMARK
I. Pasichnyk, W. Zwermann, K. Velkov, GRS Germany, S. Nikonov, VNIIAES, Moscow, Russia
KALININ-3 BENCHMARK CALCULATION WITH COUPLED CODE PARCS-ATHLET
I. Pasichnyk, K. Velkov, GRS Germany, S. Nikonov, VNIIAES, Moscow, Russia
COMPREHENSIVE ANALYSIS OF THE OECD/NES KALININ-3 BENCHMARK (PHASE 1-3) BY USING ATHLET AND ATHLET/KIKO3D COUPLED CODES
Gyorgy Hegyi, Andras Kereszturi, Istvan Trosztel, Zsolt Elter, Centre for Energy Research Hungarian Academy of Sciences, Hungary
SOLUTION OF THE OECD KALININ-3 BENCHMARK – EXERCISE 2 AND 3
Jah Hadek, UJV Rez, a. s., Czech Republik
ANALYSIS OF FUEL THERMAL CONDITION BASED ON COUPLED NEUTRONIC AND THERMAL-PHYSICAL CALCULATIONS
V.G. Artemov, L.M. Artemova, V.G. Korotayev, P.V. Miheyey, Yu.P. Shemayev, FSUE «Alexandrov NITI», Russia
REACTOR DYNAMICS MODELS FOR SAFETY ANALYSIS IN AERB
Obaidurrahman K., Avinash J. Gaikwad, Nuclear Safety Analysis Division, Atomic Energy Regulatory Board (AERB), India
ANALYSIS OF HETEROGENOUS BORON DILUTION TRANSIENTS DURING OUTAGES WITH APROS 3D NODAL CORE MODEL
Kuopanportti J., Fortum Power and Heat Ltd, Finland
ANALYSES OF BEYOND DESIGN BASIS ACCIDENT (BDBA) “HOMOGENEOUS” BORON DILUTION SCENARIOS
Andras Kereszturi, Gyorgy Hegyi, Csaba Maraczy, Istvan Trosztel, MTA EK Centre for Energy Research, Hungarian Academy of Sciences, Hungary
APPLICATION OF STATISTICAL METHODS FOR SCRAM RELIABILITY ANALYSES
Kozlachkov A.N., Bykov M.A., Siryapin V.N., Shein V.P., Tribelev A.A., OKB “GIDROPRESS”, Russia
THE USE OF REALISTIC CODES IN SOLVING THE PROBLEMS OF ANALYSIS OF REACTOR SAFETY
Semenovich O.V., Shaparau V.A., JIPNR‒Sosny of NASB Belarus
SELECTION OF FEEDBACK PARAMETER VALUES IN PREPARATION OF LOW-GROUP CONSTANT LIBRARIES FOR VARIOUS DYNAMIC CONDITIONS
V.V. Bryukhin, M.A. Uvakin, K.Yu. Kurakin, OKB «Gidropress», Russia

Nuclear applications of computational fluid dynamics (CFD)

CFD SIMULATION OF THERMAL PROCESSES IN VVER REACTORS. COMPARISON WITH THE EXPERIMENTAL DATA
Bikezin S.K., Oleksyuk D.A., NRC “Kurchatov Institute”, Moscow, Russia
APPLICATION OF COMPUTATION FLUID DYNAMICS IN NUCLEAR REACTOR SAFETY ANALYSIS
T. Hohne, Helmholtz-Zentrum Drezden-Rossendorf (HZDR), Germany
IMPLEMENTATION OF CFD MODULE IN THE KORSAR THERMAL- HYDRAULIC SYSTEM CODE
Yudov Yu.V, Danilov I.G., and Chepilko S.S. Alexandrov Research Institute of Technology (NITI), Russia
MODELING OF THERMOHYDRAULIC PROCESES IN ROD TIPE FUEL ASSEMBLIES OF WATER COOLED REACTORS
Semenovich O.V., Joint Institute of Power and Nuclear Research – Sosny, Belarus
THERMO-HYDRAULIC EFFECTS OF VVER-1000 MIXING GRIDS. POSSIBILITY TO INCREASE THE ALLOWABLE ENERGY RELEASES
Shipov D.I., Samoilov O.B., Falkov A.A., Lukyanov V.E., JSC «Afrikantov OKBM», Russia

Nuclear fuel cycle perspectives and sustainability and intermediate storage of spent fuel, decommissioning and rad waste

AER WORKING GROUP F ACTIVITIES IN 2014
Pavel N. Alekseev, Anatoly A. Dudnikov, NRC «Kurchatov institute», Russia
PROSPECTS OF SUBCRITICAL MOLTEN SALT REACTOR FOR MINOR ACTINIDES INCINERATION IN CLOSED FUEL CYCLE
P.N. Alekseev, V.Yu. Blandinsky, A.A. Dudnikov, P.A. Fomichenko, V.A. Nevinitsa, A.A. Frolov, A.S. Lubina, A.A. Sedov, A.S. Subbotin, NRC «Kurchatov institute», Russia
ALLEGRO PROJECT
Branislav Hatala, Petr Darilek, Vuje, a.s., Slovak Republic
INVENTORY AND DECAY HEAT CALCULATIONS FOR 4.0 % VVER-440 FUEL ASSEMBLY USING THE CODES SERPENT AND SNF
Tuukka Lahtinen, Fortum Power and Heat Ltd, Espoo, Finland
COMPREHENSIVE RESEARCH OF THE PRACTICAL REALISATION OF THE THORIUM NUCLEAR FUEL CYCLE
Bolshakov V.V., NRC “Kurchatov Institute” Russia; Bashkirtsev S.M., Morozov A.G., Lightbridge Corp., Virginia, USA
MODELS OF MULTI-CRITERIA ANALYSIS AND CONTROL OF PROPERTIES OF DISTRIBUTED OBJECT SYSTEM OF CLOSED NUCLEAR FUEL CYCLE
Ignatov A.A., Kormilitsyn M.V., Subbotin S.A., Alekseev P.N., Bulanova T.M., NRC «Kurchatov institute», Moscow, Russia
CORRELATION DEPENDENCIES FOR DETERMINATION OF BURNUP AND ACTINIDES CONTENT IN SPENT NUCLEAR FUEL
Zhemzhurov M.L., Serebriany G.S., Rudovich D.O., JIPNR‒Sosny of NASB, Belarus
SOME HELIOS-2 CALCULATIONS IN ALLEGRO PROJECT
Radoslav Zajac, Petr Darilek, VUJE Inc., Slovakia