21st Symposium of AER on VVER Reactor Physics and Reactor Safety

Date: 2011-09-19 -- 2011-09-23

Place: Dresden, Germany

Organized by: HZDR

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Welcome address

Opening and Welcome
S. Kliem, HZDR, Germany
Overview on the Institute of Safety Research within the Helmholtz- Zentrum Dresden- Rossendorf
S. Kliem, HZDR, Germany
Publication possibilities for AER scientific papers
A. Aszodi, Budapest University of Technology and Economics, Hungary
Safety assessment of the German NPPs after the Fukushima accident
A. Pautz, GRS, Germany

Spectral and core calculations

Information about AER WG A on improvement, extension and validation of parametrized few-group libraries for VVER 440 and VVER 1000
P. Mikoláš, SKODA JS a.s., Czech Republic
HELIOS: Application for criticality limits assessment
T. Simeonov, Studsvik Scandpower GmbH, Germany
A comparison of the FA’s models with the detailed and simplified description of the design elements in calculations by MCU code, A.S. Bikeev, S.V. Marin, E.A. Sukhino-Khomenko
NRC "Kurchatov Institute" Moscow, Russia
Development of multi-group spectral code TVS-M
A.P. Lazarenko, A.V. Pryanichnikov, NRC "Kurchatov Institute" Moscow, Russia
An analytical solution for the consideration of the effect of adjacent fuel elements; extension to hexagonal fuel elements
B. Merk, U. Rohde, HZDR, Germany
The influence of the small radial FAs displacements on the power distribution in the VVER-cores
E.A. Sukhino-Khomenko, NRC "Kurchatov Institute" Moscow, Russia
On solution to the problem of reactor kinetics with delayed neutrons
J. Kyncl, Nuclear Research Institute Řez, Czech Republic
Influence of spectral history on full core calculation results
Y. Bilodid, S. Mittag, HZDR, Germany
Effect of burnup history by moderator density on neutron-physical characteristics of WWER-1000 core
I. Ovdiienko, A. Kuchin, V. Khalimonchuk, M. Ieremenko, SSTC NRS Kiev, Ukraine
The development of the code package PERMAK-3D/SC-1
P.A. Bolobov,D.A. Oleksyuk, NRC "Kurchatov Institute" Moscow, Russia
Steps ahead in the few-group cross-section library generation at the pin level
N. Petrov, J-J. Herrero, INRNE Sofia, Bulgaria
Advanced calculation schemes and cross-section library generation in hexagonal geometry with APOLLO2
G. Todorova, N. Petrov, N. Zheleva, N.P. Kolev, F. Damian, INRNE Sofia, Bulgaria

Reactor physics experiments and code validation

"Full-Core" - VVER-440 core periphery power distribution benchmark proposal
V. Krýsl, P. Mikoláš, D. Sprinzl, J. Švarný, ŠKODA JS a.s., Czech Republic
Calculations of fission rate distribution in the core of VVER-1000 mock-up on the LR-0 reactor using alternative methods and comparison with results of measurements
S. Zaritskiy, A. Kovalishin, T. Tsvetkov, NRC “Kurchatov Institute”, Russia
Qualification of the APOLLO2 lattice physics code of the NURISP platform for VVER hexagonal lattices
A. Keresztúri, G. Hegyi, Á. Tóta, KFKI Atomic Energy Research Institute, Hungary
The simplified P3 approach on a trigonal geometry in the nodal reactor code DYN3D
S. Duerigen, E. Fridman, HZDR, Germany
Solution of the “MIDICORE” VVER-1000 core periphery power distribution Benchmark by KARATE and MCNP
E. Temesvári, G.Hordósy, G. Hegyi, Cs.Maráczy, KFKI Atomic Energy Research Institute, Hungary
Solutions for the task 1 and task 2 of the benchmark for core burnup calculations for a VVER-1000 reactor
T. Lötsch, V. Khalimonchuk, A. Kuchin, TÜV SÜD Industrie Service GmbH, Germany
Overview of the validation of a new 3-D neutronics model in APROS
J. Rintala, VTT, Finland
SP3 solution versus diffusion solution in nodal codes – which improvement can be expected
B. Merk and S. Duerigen

Core design, monitoring and fuel management

AER Working Group C activities in 2011 (oral presentation, only)
I. Nemes,Paks NPP, Hungary
In-core control system modernization experience on WWER-1000 units
A. Bykov, SNIIP Atom Ltd. Moscow, Russia
Status and prospects of the core surveillance system SCORPIO-VVER in Czech Republic and Slovakia
J. Molnar, R. Vocka, Nuclear Research Institute Řez, Czech Republic
Role of the team of scientific and technical commissioning support during Mochovce NPP Unit3&4 commissioning
J. Hermanský, M. Prachár, M. Sedlácek, VUJE Inc., Slovakia
AER Working Group B activities in 2011
P. Darilek, VUJE Inc., Slovakia
15m-cycle option for NPP Paks operation
I. Nemes, Paks NPP, Hungary
Experience of TVSA fuel implementation at Kozloduy NPP
K. Kamenov, Al. Kamenov, D. Hristov, Kozloduy NPP, Bulgaria
Implementation of 5-year fuel cycle strategy for control fuel assemblies at Dukovany NPP
J.Bajgl, ČEZ, a.s., Dukovany NPP, Czech Republic
New practice for the evaluation of rod efficiency measurement by rod drop at the NPP Paks
I. Pós, T. Parkó, Paks NPP, Hungary
VVER 440 fuel cycles optimization by the ATHENA code
J. Prehradný, SKODA JS a.s., Czech Republic
Some remarks to the pin-wise power distribution behavior in L3P core designs
M. Fiala, ČEZ, a.s., Dukovany NPP, Czech Republic
Investigation of gamma radiation share in full SPND signal
A.Y.Kurchenkov, A.S. Kulakov, N.I. Alexeev, A.E. Kalinushkin, NRC "Kurchatov Institute" Moscow, Russia

Reactor dynamics and safety analysis

AER Working Group D on VVER safety analysis – report of the 2011 meeting
S. Kliem, HZDR, Germany
Preliminary results of the seventh three-dimensional AER dynamic benchmark problem calculation. Solution of problem with DYN3D- and RELAP5-3D-codes
M. Bencik, J. Hádek, Nuclear Research Institute Řez, Czech Republic
Simulation of AER-7 benchmark with the coupled code DYN3D/ATHLET
Y. Kozmenkov, S. Kliem, HZDR, Germany
COBAYA3/FLICA4 vs. DYN3D/FLOCAL Solutions of the VVER- 1000 MSLB benchmark
I. Spasov, T. Tzanov, N. Kolev, J. Hadek, INRNE Sofia, Bulgaria
Modeling the spatial distribution of the parameters of the coolant in the reactor volume
S.P. Nikonov, NRC "Kurchatov Institute" Moscow, Russia
Comparisons with measured data of the simulated local core parameters by the coupled code ATHLET-BIPR-VVER applying a new enhanced model of the reactor pressure vessel
S.P. Nikonov, I. Pasichnyk, K. Velkov, GRS, Germany
WWER safety analysis in case of simultaneous positive reactivity introduction by control rods withdrawal and pure condensate injection
A. Kuchin, I. Ovdiienko, V. Khalimonchuk, SSTC NRS Kiev, Ukraine
Study on severe accidents and countermeasures for VVER-1000 reactors using the integral code ASTEC
P. Tusheva, N. Reinke, F. Schäfer, E. Altstadt, S. Kliem, HZDR, Germany
Computational and design considerations for innovative Light Water Reactor with natural circulation
A. Soldatov, T. S. Palmer, Oregon State University, USA
Studies on boiling water reactor design with reduced moderation and analysis of reactivity accidents using the code DYN3D-MG
U. Rohde, HZDR, Germany
Application of DYN3D/ATHLET and DYN3D/RELAP5 coupled codes to simulation of RUTA-70 reactor with CERMET fuel
Y. Kozmenkov, Y. Baranaev, A. Glebov, U. Rohde, HZDR, Germany

Spent fuel disposal, actinide transmutation

AER Working Group E activities in 2011
V. Chrapciak, VUJE Inc., Slovakia
Criticality safety analysis of fresh and spent fuel storage and handling for NPP Mochovce using MCNP5
G. Farkas, J. Haščík, J. Lüley, B. Vrban, M. Petriska, V. Slugeň, P. Urban, Slovak University of Technology in Bratislava, Slovakia
VVER-440 with viable direction to sustainability
P. Darilek, C. Strmensky, R. Zajac, J. Majercik, VUJE Inc., Slovakia
Comparison of square and hexagonal fuel lattices for high conversion PWRs
D. Kotlyar, E. Shwageraus, Ben-Gurion University of the Negev, Israel
ALLEGRO - Introduction to GFR
P. Darilek, R. Zajac, VUJE Inc., Slovakia
Summary of 13th session of the AER Working Group F- "Spent fuel transmutations" and 4th meeting of INPRO project RMI – "Meeting energy needs in the period of raw materials insufficiency during the 21st century"
V Lelek, Nuclear Research Institute Řez, Czech Republic
Strategies of the future technological development
V. Lelek, Nuclear Research Institute Řez, Czech Republic

Nuclear applications of three dimensional thermal hydraulics

AER Working Group G activities in 2011
A. Aszódi, Budapest University of Technology and Economics, Hungary
Investigation of coolant mixing in VVER-440/213 RPV with improved turbulence models
B. Kiss, A. Aszódi, Budapest University of Technology and Economics, Hungary
New studies of the natural convection around the fuel rod model of the BME training reactor with PIV/LIF technique
R. Szijártó , A. Aszódi, B. Yamaji, Budapest University of Technology and Economics, Hungary
Effect of spacer grid mixing vanes on coolant outlet temperature distribution
T. Rämä, T. Lahtinen, Fortum Power and Heat Ltd., Finland
Analysis of coolant flow in central tube of VVER-440 fuel assemblies
G. Zsíros, S. Tóth, A. Aszódi, Budapest University of Technology and Economics, Hungary
Analysis of С1 experiment on UPTF facility with an advanced ATHLET model
I. Pasichnyk, K. Velkov, S.P. Nikonov, GRS, Germany
A proposal to continuation of VVER-440 fuel assembly head benchmark
A. Aszódi, S. Tóth, Budapest University of Technology and Economics, Hungary

Engineering factors

Information about Group H meeting
L.K. Shishkov, NRC "Kurchatov Institute" Moscow, Russia
Estimation procedure for engineering margin factors of VVER fuel cycles
V.G. Dementiev, D.A. Oleksuk, L.K. Shishkov, NRC "Kurchatov Institute" Moscow, Russia
Account for uncertainties of control measurements in estimations of design margin factors
V.G. Dementiev, V.D. Sidorenko, L.K. Shishkov, NRC "Kurchatov Institute" Moscow, Russia
Specific features of accounting for probable power excursions at periphery FAs, which are caused by FA gaps behaviour in the course of VVER-1000 operation
E.F. Michailov, L.K. Shishkov, NRC "Kurchatov Institute" Moscow, Russia