20th Symposium of AER on VVER Reactor Physics and Reactor Safety

Date: 2010-09-20 -- 2010-09-24

Place: Hanasaari, Espoo, Finland

Organized by: VTT / Fortum

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Welcome address

Opening of the symposium
K. Larjava, VTT, Finland
Welcome address
P. Lundström, Fortum, Finland
Finnish Research Programmes on Nuclear Safety
E. K. Puska, VTT, Finland
STUK Preliminary Safety Assessment of New Nuclear Power Plants
R. Sairanen, STUK Radiation and Nuclear Safety Authority, Finland
Renewal or AER
I. Vidovszky, KFKI AEKI, Hungary (Oral presentation)

Spectral and Core Calculations

Information of AER WG A on improvement, extension and validation of parametrized few-group libraries for VVER-440 and VVER-1000
P. Mikoláš, Škoda JS a.s., Czech republic
SERPENT Monte Carlo reactor physics code
J. Leppänen, VTT, Finland
HELIOS2: simple procedutre for generating few group homogenized parameters for non-multiplying domain in hexagonal geometry
T. Simeonov, Studsvik Scandpower GmbH., Germany
Quadriga and Kirke - front end applications for HELIOS
F. Havlůj, R. Vočka, Nuclear Research Institute Rez, Czech Republic
A nodal SP3 approach for reactors with hexagonal fuel assemblies
S. Duerigen, U. Grundmann, S.Mittag, B. Merk, S. Kliem, FZD, Germany
Application of Discontinuity factors in C-PORCA 7 code
I. Pós, T. Parkó, S. Patai Szabó, Paks NPP Ltd, Hungary (presented by I. Nemes)
MCU calculation of spacing grid influence on FA's axial power distribution
S.S. Gorodkov, L.K. Shishkov, E.A. Suhino-Homenko, RRC Kurchatov Institute, Russia
Calculation of CPNB44 ex-core detector weighting functions for VVER using MCNP5
G. Farkas, V. Slugeň, J. Haščík, Slovak University of Technology, Slovakia

Reactor physics experiment and code validation

Calculation of Novovoronezh re-criticality experiment with CASMO/HEXBU code system
M. Antila & S. Saarinen, Fortum Nuclear & Thermal, Finland
Validation of the KARATE-440 code system by Analysis of recriticality measurement of Novovoronesh NPP. A. Keresztúri
Gy. Hegyi,A. Molnár, KFKI AEKI, Hungary
Accuracy estimation for the calculation of the core state at VVER-1000 reactor with incomplete fuel overlapping by the absorber
A.V.Tikhomirov, G.L.Ponomarenko, OKB “Gidropress”, Russia
Selected examples on multiphysics researches at KFKI AEKI
I. Panka, A. Keresztúri, C. Maráczy, KFKI AEKI, Hungary
'MIDICORE' VVER-1000 core periphery power tilt benchmark proposal
V. Krýsl, P. Mikoláš, D. Sprinzl, J. Švarný, ŠKODA JS a.s., Czech Republic
MCU participation in MIDICORE benchmark
S. S. Gorodkov, E.A.Suhino-Homenko, RRC Kurchatov Institute, Russia
Core periphery power tilt benchmark for VVER-440
definition. P. Darilek, V. Chrapciak, J. Majercik, VUJE, Inc., Slovakia
Corrections and additions to the proposal of a benchmark for core burnup calculations for a VVER-1000 reactor
T. Lötsch, V. Khalimonchuk, A. Kuchin, TÜV SÜD, Germany, presentation
Influence of operational parameters on DPA in reactor pressure vessel of VVER-440 reactor
M. Stacho, G. Farkas, V. Slugeň, S. Sojak, Slovak University of Technology, Slovakia
Justification of the radiation load calculation procedure for VVER reactor vessels
A.D. Dzhalandinov, V.I. Tsofin, OKB “Gidropress”, Russia
The VVER Core Physics, Reactor Dosimetry, and Shielding Researches in the LR-0 Reactor
S. Zaritskiy, A. Egorov, RRC Kurchatov Institute, Russia; B. Ošmera, M. Mařik, V.Rypar, M. Košťál, NRI, Řež, Czech Republic; F. Cvachovec, University of Defense, Czech Republic

Core Design and Operation

AER Working Group B activities in 2010
P. Dařílek, VÚJE Trnava Inc., Slovakia
Review of core design and operating experience in Loviisa
T. Lahtinen, M. Antila & S. Saarinen. Fortum Nuclear & Thermal, Finland
Introduction of Gd-2 fuel to Paks NPP Units
I. Nemes, Zs. Szécsényi, T. Parkó, I. Pós., Paks NPP Ltd., Hungary
Introduction of In-Core fuel management for TNPS
Li Youyi, Jiangsu Nuclear Power Corporation, China
Fuel cycles of VVER
V.V. Morozov, V.V. Saprykin, RRC Kurchatov Institute, Russia
Challenging cycles of Dukovany NPP with highly enriched fuel optimized by the Athena code
K. Katovsky, SKODA JS, a.s.; F. Fej & J. Prehradny, Czech Technical University; R. Čada, University of West Bohemia, Czech Republic
VVER-440 Fuel Cycles Possibilities Using Modified FA Design
P. Mikoláš, ŠKODA JS a.s., Czech Republic
Progress at the 5-year fuel cycle strategy implementation at Dukovany NPP
J. Bajgl, CEZ Inc., Dukovany NPP, Czech Republic

Core Monitoring

Summary on the activity of AER’s Working Group on core monitoring (flux reconstruction, in-core measurements)
I. Nemes, Paks NPP Ltd
Reload Startup Physics Tests for TNPS. X. Yang
Jiangsu Nuclear Power Corporation, Tianwan NPS
Preparation of physics commissioning of Mochovce units 3 & 4
M. Sedlacek, V. Chrapčiak, VUJE, Inc., Slovakia
Operational experience with neutron power on-line calibration system AKE-02R at Bohunice NPP
M. Závodský, K. Klučárová, VUJE Inc., Slovakia
SCORPIO-VVER Core Monitoring and Surveillance System for VVER-440 Reactors
J. Molnar, R. Vocka, Nuclear Research Institute Rez plc, Czech Republic
Reconstruction of core inlet temperature distribution by cold leg temperature measurements
S. Saarinen, M. Antila, Fortum Nuclear & Thermal, Finland
Primary circuit and reactor core T-H characteristics determination of WWER 440 reactors
J. Hermanský, V. Petényi, M. Závodský, VUJE Inc., Slovakia

Reactor dynamics and safety analysis

Working group on VVER safety analysis - report of the 2010 meeting
S. Kliem, FZD, Germany
Study of transient connected with WWER-1000 cluster drop with subsequent working of automatic power controller
A.Kuchin, I.Ovdiienko, V.Khalimonchuk, SSTC N&RS, Ukraine
Effect of burnup dependence of fuel cladding gap properties on WWER core characteristics
M. Ieremenko & I.Ovdiienko SSTC N&RS, Ukraine
Sensitivity Analysis of CRE accident
S. Bznuni, NRSC, Armenia
Coupling of the CFD code ANSYS CFX with the 3D neutron kinetic core model DYN3D
S. Kliem, A. Grahn, U. Rohde. FZD; J. Schuetze, Th. Frank, ANSYS Germany GmbH, Germany
LUT infrastructure for VVER safety studies
R. Kyrki-Rajamäki, J. Laine, T. Merisaari, V. Riikonen, A. Räsänen, H. Purhonen, Lappeenranta University of Technology, Finland
Validation of new 3-D neutronics model in APROS for hexagonal geometry
J. Rintala, VTT, Finland
Definition of the 7th dynamic AER benchmark - VVER-440 pressure vessel coolant mixing by re-connection of an isolated loop
A. Kotsarev, M. Lizorkin, R. Petrin, RRC Kurchatov Institute, Russia
Benchmark calculation with improved VVER-440/213 RPV CFD model
B. Kiss, A. Aszodi, Budapest University of Technology and Economics, Hungary
Comparison of In-Core Thermocouple and SPND Measured Data with the ATHLET-BIPR-VVER Predictions
S.P. Nikonov, RRC Kurchatov Institute, Russia; K. Velkov, A. Pautz, GRS mbH, Germany
Peculiarity by Modeling of the Control Rod Movement by the Kalinin-3 Benchmark
S.P. Nikonov, RRC Kurchatov Institute, Russia; K. Velkov, A. Pautz, GRS mbH, Germany

Nuclear applications of three-dimensional thermal hydraulics

Summary on the activity of working group
G. A. Aszódi, Budapest University of Technology and Economics, Hungary
3D PORFLO simulations of Loviisa steam generator
V. Hovi & M. Ilvonen, VTT, Finland
Study of thermal stratification and mixing using PIV
B. Yamaji, R. Szijártó, A. Aszódi, Budapest University of Technology and Economics, Hungary
Experimental Investigation of Coolant Mixing in VVER and PWR Reactor Fuel Bundles by Laser Optical Techniques for CFD Validation
D. Tar, G. Baranyai, Gy. Ézsöl, I. Tóth, KFKI AEKI, Hungary
Study on Natural Convection around a vertical heated rod using PIV/LIF technique
R. Szijártó, B. Yamaji, A. Aszódi,Budapest University of Technology and Economics, Hungary
Fuel assembly head CFD study with comparison against in-core thermocouple readings at the Loviisa NPP. K. Myllymäki
S. Saarinen, Fortum Nuclear & Thermal, Finland
Introduction of VVER-440 Fuel Assembly Head CFD benchmark. A. Aszódi
S. Tóth, Budapest University of Technology and Economics, Hungary
Results of VVER-440 fuel assembly head benchmark. M. Bykov
A. Shishov, O. Kudryavtsev, D. Posysaev, OKB “GIDROPRESS”, Russia
A simplified approach to VVER-440 fuel assembly head benchmark. P. Mühlbauer
NRI Rez plc, Czech Republic
Results of VVER-440 Fuel assembly head CFD benchmark. K. Myllymäki
Fortum Nuclear & Thermal, Finland
Summary of results of VVER-440 Fuel Assembly Head CFD Benchmark. A. Aszódi
S. Tóth, Budapest University of Technology and Economics; I. Farkas, KFKI AEKI; K. Myllymäki, Fortum Power & Heat; P. Kodl, Skoda JS a.s., P. Mühlbauer, NRI Rez plc; D. Posysaev, OKG “GIDROPRESS”; J. Remis, VUJE a.s.

Criticality, spent fuel, decommissioning

Information about AER working group E on physical problems of spent fuel, radwaste, decommissioning
V. Chrapciak, VUJE, Inc., Slovakia; L.Marková, NRI Rez, Czech Republic
Impact of burnable absorber Gd on nuclide composition for VVER-440 fuel (Gd-2)
R. Zajac & V. Chrapciak, VUJE, Inc., Slovakia

Transmutations of spent fuel and future nuclear energy

Summary of 12th session of the AER Working Group F – "Spent Fuel Transmutations" and 3rd meeting of INPRO Project RMI – "Meeting energy needs in the period of raw materials insufficiency during the 21st century". V. Lelek
Nuclear Research Institute Rez, Czech Republic
VVER-440 IMF core calculations
P. Darilek, R. Zajac, C. Stremensky, J. Majercik, VUJE, Inc., Slovakia, presentation
Considerations about energy
V. Lelek, Nuclear Research Institute Rez, Czech Republic
About energy vision in the 21st century and the role of ecological resources
V. Lelek, Nuclear Research Institute Rez, Czech Republic

Engineering factors

Summary of the special AER group meeting "Elaboration of the methodology for calculating the core design engineering factors”
S. V. Tsyganov, RRC Kurchatov Institute, Russia
Components of VVER engineering factors for peaking factors: status and trends
S. V. Tsyganov, RRC Kurchatov Institute, Russia
Determination of engineering safety factor -routine in Hungary (a methodology for the normal operation local power engineering safety factors)
Z. Szécsényi, L. Korpás, G. Bóna, Paks NPP Ltd, Hungary & A. Keresztúri KFKI AEKI, Hungary
Some remarks about engineering factor determination
J. Švarný, ŠKODA JS a.s., Czech Republic
A possible way for conservatism reduction at the modelling of VVER operational modes
L.K. Shishkov, RRC Kurchatov Institute, Russia, presentation (also in russian)
Assessment of the influence of design limits to the economics of VVER fuel cycle
V.G. Dementiev, L.K. Shishkov, RRC Kurchatov Institute, Russia