Programme
Programme
CONFERENCE LANGUAGE
English will be used for all written presentations (for example PowerPoint) & written materials (programme, Book of Abstracts, conference website, etc).
Simultaneous interpreting: Czech, Russian and English (only Pleanary section, language of the paralel section will be English - without simultaneous translation).
VVER 2019 - SCHEDULE
10 NOVEMBER 2019 - SUNDAY
18.00 - 20.00, Registration
19.00 - 21.00, Welcome Drink
11 NOVEMBER 2019 - MONDAY
08.00, Registration
09.00 - 10.00, Opening Ceremony, Welcome Speeches
10.00 - 18.30, Sections
10.40 - 11.00, Coffee Break
12.30 - 13.45, Lunch
15.30 - 15.50, Coffee Break
19.00 - 24.00, Conference Dinner
12 NOVEMBER 2019 - TUESDAY
08.30, Registration
09.00 - 17.40, Sections
11.00 - 11.30, Coffee Break
13.00 - 14.15, Lunch
15.50 - 16.10, Coffee Break
17.40 - 18.00, Closure of the Meeting
13 NOVEMBER 2019 - WEDNESDAY
Technical Excursion
VVER 2019 - RECENT & FUTURE - PROGRAM
SUNDAY, NOVEMBER 10, 2019
18.00 - 20.00
Registration
19.00 - 21.00
Welcome Cocktail
MONDAY, NOVEMBER 11, 2019
08.00
Registration
09.00 - 10.00
OPENING CEREMONY
ORGANIZER OPENING SPEECHES
BURKET D., President, CNS (Czech Nuclear Society)
ŽIDOVÁ L., Member of the Board of Directors, ÚJV Řež, a. s.
WELCOME ADDRESS
LAIRD A., President, ENS (European Nuclear Society)
EHLER T., Director of the Nuclear Power Department, Ministry of Industry and Trade CR
GRÉGR M., Former Minister, Ministry of Industry and Trade CR
MARGELOV S., Rosatom Central Europe
ZÁVODSKÝ P., Director, New Nuclear Power Plants Construction, ČEZ, a. s.
MOSTECKÝ M., Member of the Board of Directors, ŠKODA JS a. s.
10.00 - 10.40
NUCLEAR ENERGY POLICY
Chairperson: BURKET D., President, CNS (Czech Nuclear Society)
LAIRD A., President, ENS (European Nuclear Society)
EHLER T., Director of the Nuclear Power Department, Ministry of Industry and Trade CR
10.40 - 11.00
Coffee Break
11.00 - 12.30
LICENSING, LTO (LONG TERM OPERATION)
Chairperson: BURKET D., President, CNS (Czech Nuclear Society)
KŘIVÁNEK R., IAEA
Long term operation of nuclear power plants – 2015 – 2018 IAEA SALTO mission observations and trends
USHAKOV A., Rusatom Service
EXPERIENCE OF RUSATOM SERVICE JSC ON LIFETIME EXTENSION PROJECT IMPLEMENTATION FOR NPPs WITH VVER-440 AND VVER-1000 REACTORS: KEY OBJECTIVES, ASPECTS AND CHALLENGES
HALA P., ČEZ, a. s.
License Renewal of NPP Dukovany
RITTER T. J., Technetics GROUP
Nuclear sealing technology and flange refurbishment for aged equipment of VVER NPP units
12.30 - 13.45
Lunch
13.45 - 15.30
LICENSING, LTO (LONG TERM OPERATION)
Chairperson: BURKET D., President, CNS (Czech Nuclear Society)
SCHUMMER B., Framatome
ASSESSMENT OF VALVE STATE BY IN-SITU METALLOGRAPHY AS COST SAVING TOOL FOR MAINTENANCE ACTIVITIES
ANTONCHENKO V., IPP-Center LLC
LIFETIME EXTENSION OF VVER-1000 RPV FROM FRACTURE MECHANICS POINT OF VIEW
ZARAZOVSKII M., IPP-Center LLC
Actual problems of assessing the technical state of WWER-1000 reactor elements for justification of lifetime prolongation
VOLTR V., ÚJV Řež, a. s.
GADUS (Graphics Aided Document Utilization System)
KRONĎÁK M., ÚJV Řež, a. s.
Aspect and Components of Flow Accelerated Corrosion Ageing Management Program
15.30 - 15.50
Coffee Break
15.50 - 17.30
POWER UPRATES, AVAILABILITY, OPERATION, SAFETY, AND CAPACITY FACTORS INCREASING
Chairperson: DUSPIVA J., ÚJV Řež, a. s.
LATORRE R., Framatome
Monitoring and diagnostic solutions for component reliability and condition based maintenance for VVER
HAKL V., ÚJV Řež, a. s.
Functional Analysis (FA) and Software Tool for proof of NPP Robustness and Independence of Individual Levels in Defence in Depth
PLISKA J., I&C Energo
NPP Thermal Performance Monitoring and Optimization System
BROM J., Centrum výzkumu Řež (CVŘ)
3D profilometry utilization on VVER type reactors
HLAVÁČ Z., Centrum výzkumu Řež (CVŘ)
Practical use of nonlinear ultrasound methods, monitoring the radiation induced ageing of concrete biological shielding of WWER 440/213 reactors
17.30 - 18.30
NUCLEAR FUEL
Chairperson: VITANZA C., Independent Consultant, Norway
Panel on Experimental Support Needs for VVER after Halden Reactor Project
(PAZDERA F., KINNUNEN P., HÖGLUND J., SHISHKIN A., KLOUZAL J.)
18.30
End of the first day
19.00 - 24.00
Networking Dinner, room Belvedere
TUESDAY, NOVEMBER 12, 2019, PLENARY SECTION, ROOM PRAGUE A - C
08.00
Registration
09.00
Open Speech
09.15 - 11.00
NEW BUILDS, Chairperson: ŠÍMA Z., Rosatom Central Europe
TOMÍČEK L., Senior Vice-President, Rusatom Overseas Inc
Evolution of VVER reactors and current performance
KATSMAN A., JSC "Concern Rosenergoatom"
Experience gained with new power units commissioning in Russia
KOUKLÍK I., Fennovoima
Hanhikivi NPP - Current Status
ČERNÝ V., ČEZ, a. s.
Latest Update on Preparation for the New Nuclear Project
MOROZOV V., Atomenergoproekt
Safety of NPP with VVER new generation
11.00 - 11.30
Coffee Break
11.30 - 13.00
NEW BUILDS, Chairperson: ŠÍMA Z., Rosatom Central Europe
RTISCHEV N., Rusatom Overseas
SMR project in Rosatom
PAZDERA F., ALVEL, a. s.
Potential for nuclear energy use in the heat supply in Czech Republic
KOKAREV I., Assystem France
VVER Licensing according to Western Regulation
WABER P., Framatome
Qualification Strategie for Cost Reductions in New Build and LTO Programs
ZRNIĆ I., Reaktortest s. r. o.
Application of non-destructive techniques in pre-operation nuclear power plants
FIALA J., DOOSAN ŠKODA POWER
DOOSAN ŠKODA POWER is ready for a new nuclear unit in the Czech Republic
VYVADIL J., ÚJV Řež, a. s., ENERGOPROJEKT PRAHA
ENERGOPROJEKT PRAHA activities on the nuclear new builds in the world
13.00 - 14.15
Lunch
14.15 - 15.50
POWER UPRATES, AVAILABILITY, OPERATION, SAFETY, AND CAPACITY FACTORS INCREASING
Chairperson: DUSPIVA J., ÚJV Řež, a. s.
KOTOUČ M., ÚJV Řež, a. s.
Analytical support for strategies of In-Vessel core cooling and Ex-Vessel corium confinement for the Temelin NPP
LITYSHEV A., JSC "OKB Gidropress"
"OKB Gidropress" participation in development of SA strategy for NPP-2006 (AES-2006)
ASTAKHOV V., JSC "OKB Gidropress"
Methodological approaches and experience in performing severe accidents analyses for NPPs with VVER-440 RP
MAZUROK O., ES Group Europe s.r.o.
Filtered containment venting systems for Ukrainian NPP units with reactor facility V-320
KOSTOV E., Westinghouse Germany
Long Term Containment Cooling for VVER-440
BERKY R., ROEZ
Experience gained from numerical analysis of RPV in conditions of core melting accident
15.50 - 16.10
Coffee Break
16.10 - 17.20
POWER UPRATES, AVAILABILITY, OPERATION, SAFETY, AND CAPACITY FACTORS INCREASING
Chairperson: DUSPIVA J., ÚJV Řež, a. s.
AMER D., NRNU "MEPhi"
The effect of Reactor Power Behavior on LBLOCA hydrodynamics
MOROZOV A. V., State Scientific Centre of RF
Experimental study for the substantiation of the operability of VVER passive safety systems
ALLORY M., Framatome
FGPA-Based Compact Safety Controller
KANATOV S., Atomtechenergo
Projects on electrical power generation level enhancing and on capacity enhancing for NPP with PWR-type reactors
RUCHAŘ M., ŠKODA JS, a. s.
CRDM type LKP-M/4: the newest control rod drive mechanism from ŠKODA JS
NOVÝ L., ZAT a. s.
New generation of the RRCS system for control of the LKP-M/4 drives in the I&C projects of the VVER 1000 and VVER 1200 reactors
17.20 - 17.30
Closing Ceremony
BURKET D., President, CNS (Czech Nuclear Society)
ŽIDOVÁ L., Member of the Board of Directors, ÚJV Řež, a. s.
PARALLEL SECTION, ROOM PRAGUE D
08.00
Registration
09.00
Open Speech
09.15 - 11.00
FUEL CYCLE ISSUES, Chairperson: BĚLÁČ J., ALVEL, a. s.
LINHART S., ŠEVEČEK M., ALVEL, a.s.
Highlights of 2019 TOP FUEL and Nesebar WWER FUEL conferences
KINNUNEN P., VTT Technical Research Centre of Finland
UPDATE OF THE JHR EXPERIMENTAL CAPACITY for VVER community utilization
WWER FUEL
HÖGLUND J., Westinghouse Electric Sweden AB
Westinghouse VVER-1000 Fuel Design and Delivery to Temelín Nuclear Power Plant
SHISHKIN A., TVEL
The Major Areas of Cooperation between TVEL JSC and Czech Companies
LINHART S., ALVEL
Material Research of advanced zirconium-based alloys irradiated at Temelin NPP Reactor Core
KREJČÍ J., UJP PRAHA
The oxidation behavior of E110 cladding alloy in air-steam mixtures
LUKYANOV V. E., JSC Afrikantov OKBM
Advanced TVSA fuel for VVER-1000
11.00 - 11.30
Coffee Break
11.30 - 13.00
ATF
MIKLOŠ M., Centrum výzkumu Řež (CVŘ)
UJV group activities in the qualification of Accident Tolerant Fuels
ROMASHOV Y., Kharkiv Polytechnic Institute
INFLUENCING THE THIN COATING ON THE STRESS-STRAIN STATE OF THE CLADDING OF FUEL RODS OF THE VVER-1000 NUCLEAR REACTOR
KOPEĆ M., Centrum výzkumu Řež (CVŘ)
Debris fretting impact on the standard and coated Zr-1%Nb cladding evaluation
FUEL STORAGE
ŠEVEČEK M., ČVUT, FJFI
Introduction of the Temelin Irradiated Cladding Project - TIRCLAD
KOSIAK P., University of West Bohemia
RADIATION SAFETY ANALYSIS OF CONTAINER FOR SPENT FUEL FROM VVER-440 REACTOR
13.00 - 14.15
Lunch
14.15 - 15.50
DECOMMISSIONING, Chairperson: DUBSKÁ L., NUVIA a. s.
TININ V., TVEL
Decommissioning of Nuclear Facilities and RW Management
MIKULÁŠEK M., ŠKODA JS, a. s.
Dismantling of Steam Generators at Jaslovské Bohunice V1 NPP
KRUPA P., JAVYS (Nuclear and Decommissioning Company)
Preparation and commencement of the V1 NPP decommissioning
KLEIN T., JAVYS (Nuclear and Decommissioning Company)
Implementation of the 1st stage of the V1 NPP decommissioning and use of the civil building CB 490 (turbine hall) for the needs of the V1 NPP decommissioning
15.50 - 16.10
Coffee Break
16.10 - 17.20
EDUCATION, TRAINING, R&D, ..., Chairperson: DOSTÁL V., ČVUT (Czech Technical University)
PONOMARENKO A., Rosatom Corporate Academy
Nuclear education in Russia: Professional community and collaboration
ASPIDOV V., Rosatom Technical Academy
Rosatom Technical Academy of the personnel training for NPPs under construction
ČECHÁK T., ČVUT, FJFI
Nuclear Education in the Czech Republic
KOROLYOV A. V., Odessa National Polytechnic University
Investigation of the thermoacoustic oscillations mechanism on nuclear core
NÝVLT S., ÚJV Řež, a. s.
Evaluation of containment dose rate during postulated severe accident for the Temelin NPP
ABOU-GABAL H., Alexandria University
Virtual Reality Simulation of Station Blackout Accident in VVER-1000
17.20 - 17.30
Closing Ceremony
BURKET D., President, CNS (Czech Nuclear Society)
ŽIDOVÁ L., Member of the Board of Directors, ÚJV Řež, a. s.
POSTERS
KRÁL P., ÚJV Řež, a. s.
Safety Assessment of DEC-A Events for the Czech NPP’s
IVANOV V., MAZUROK O., ES Group Europe s.r.o.
Monitoring of the spent fuel pool level including during severe accidents
ZANDER A., Framatome
Aging Management Software Platform for Long Term Operation VVER (COMSY)
FILONOVA Y., IPP-Center LLC
CHANGES IN HEAT TRANSFER CONDITIONS DUE TO THE CONTACT OF THE CORE BAFFLE AND BARREL DURING SWELLING PROCESSES
FILONOV V., IPP-Center LLC
UPPER BLOCK COOLING MODEL AND ITS APPLICATION FOR THE LIFETIME EXTENSION
AHEIEV S., IPP-Center LLC
Specific issues in lifetime prolongation of components, structures and pipelines of Ukrainian NPP's
GHONEIM A. M., Alexandria Uni
VVER 1000 SBLOCA model using RELAP5/SCDAPSIM
ZDAREK J. et al., ÚJV Řež, a. s.
THE RPV INTEGRITY ASSESSMENT WITH RESPECT TO THE CORIUM RETENTION DURING SA.
THE OECD/NEA CAPS PROJECT PROPOSAL AND RELATION TO THE IVMR EXPERIMENT
RABOCHOVÁ M., CVŘ
Severe Accident Laboratories in Research Centre Řež
RABOCHOVÁ M., CVŘ
Design Basis Accident Laboratories in Research Centre Řež
GULDNER M., Framatome
Small-Power EDGs in different applications
WEBER Ch. da Silva, Framatome
Challenges for the design of HVAC (Heating, Ventilation and Air Conditioning) systems and components for modern NPP projects
LIEBIG J., Framatome
Hydrogen Monitoring in Belarus NPP
MAZUROK O., IVANOV V., KOCHARYANTS O., ES Group Europe s.r.o.
Filtered containment venting systems for Ukrainian NPP units with reactor facility V-320
FEDOROV D., NTU
Transfer matrix method application for the hydrogasdynamic phenomena analysis
SCHUMMER B., Framatome
OPTIMIZATION OF SAFETY VALVE MAINTENANCE AND SETTING USING HOT ADJUSTMENTS TEST ON A TEST LOOP
LOSCH N., Framatome
Retrofit of Filtered Containment Venting System for VVER 1000 (Ukraine)
New ways to overcome layout restraints by Innovative Design for a well Proven and Tested Technology
NINCIC V., RAMANOVIC B., Framatome
Probabilistic SSI Analysis of a Reactor Building to Facilitate Fragility Assessment