26th Symposium of AER on VVER Reactor Physics and Reactor Safety

Date: 2016-10-10 -- 2016-10-14

Place: Helsinki, Finland

Organized by: Fortum

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Opening of the Symposium

Tiina Tuomela, Executive VP, Generation, Fortum
Vesa Ruuska, Nuclear Safety Director, Fennovoima
Tomi Routamo, Deputy Director, Operating Nuclear Power Plants, STUK

Advances in spectral and core calculation methods

Information about AER working group A
P. Mikoláš (Dr), ŠKODA JS a.s.
Advances in HELIOS2 nuclear data library
C. Wemple (Dr), Studsvik Scandpower Inc.
Some uncertainty results obtained by the statistical version of the KARATE code system
I. Panka (Dr), Hungarian Academy of Sciences, Centre for Energy Research
Accounting of boron‐10 content changes in boric acid during fuel burnup in reactor VVER‐1000
M. Sumarokov (Mr), NRC Kurchatov Institute
ANDREA 2.2 ‐ advances in modeling of VVER cores, ÚJV Řež
R. Vočka (Dr), a.s.

Reactor physics experiments and code validation continues

VVER‐440 Full‐Core Benchmark by Spectral Codes, VUJE
R. Zajac (Dr), a.s.
'Full‐Core' VVER‐440 extended calculation benchmark
D. Sprinzl (Dr), ŠKODA JS a.s.
Proposal of 'Full‐Core' VVER‐1000 calculation benchmark
D. Sprinzl (Dr), ŠKODA JS a.s.
Monte Carlo Calculations of VVER‐440 and VVER‐1000 full‐scale cores by MCU code
D. Oleynik (Mr), NRC "Kurchatov institute"
Comprehensive solution of the „MIDICORE” Benchmark by the KARATE and MCNP code system, Centre for Energy Research
G. Hegyi (Mr), Hungarian Academy of Sciences
AER X2 benchmark draft decision with use of PARCS code
M. Ieremenko (Mr), SSTC N&RS
The X2 Benchmark for VVER‐1000 Reactor Calculations. Overview and Current Status
T. Lötsch (Dr), TÜV SÜD
Calculation of VVER Benchmarks by Codes Included into Software Package KASKAD
A. Shcherenko (Ms), NRC "Kurchatov institute"
Calculating Neutron Dosimeter Activation in Vver‐440 Surveillance Chains with Serpent
T. Viitanen (Dr), VTT
Antti Räty, VTT Technical Research Centre of Finland
Testing of DYN3D Nodal and Pin‐power Simulation of VVER‐1000 Mini‐ core, ÚJV Řež
J. Hádek (Dr), a.s.
Advanced Physical Startup Test for VVER‐1200 of Novovoronezh NPP: Technique and Some Results
S. Tsyganov (Mr), NRC "Kurchatov institute"
Calculations of VVER‐1000 Start‐Up Physics Tests Using the MCU Monte Carlo Code
D. Oleynik (Mr), NRC "Kurchatov institute"

Fuel management issues

AER working group B activities in 2016, VUJE
R. Zajac (Dr), a.s
Recent improvements and operating experiences of Loviisa NPP fuel loadings
S. Saarinen (Mr), Fortum
New engineering safety factors for Loviisa NPP core calculations
J. Kuopanportti (Mr), Fortum
Experiences with 15m cycles in Paks NPP
I. Nemes (Dr), MVM Paks NPP
Core Loadings Optimisation in Dukovany NPP, ČEZ, a.s.
J. Bajgl (Mr), Dukovany NPP
Influence of time duration of FAs in spent fuel pool on VVER‐440 N‐Ph characteristics after reloading
P. Mikoláš (Dr), ŠKODA JS a.s.
Development of Fuel Cycles With New Fuel for VVER‐440. Fuel Rods with 8.9 mm External Diameter: Preliminary Assessment of Operating Efficiency
A. Gagarinskiy (Mr), NRC "Kurchatov institute” (presented as poster)
Status of ALLEGRO Project at VUJE, VUJE
R. Zajac (Dr), a.s. 10:15 Coffee break

Core surveillance and monitoring continues

AER WG C activity in 2016
I. Nemes (Dr), MVM Paks NPP 10:15 Coffee break
16 Years of Reliable Operation of the SCORPIO‐VVER Core Monitoring System at Slovak and Czech NPPs, ÚJV Řež
J. Molnár (Dr), a.s.
Verification and Development Experience of Core Monitoring System (CMS) Physical Calculation Codes for Water Cooled Water Moderated Reactors at the Software and Hardware Instrument “Kruiz” Basis
A. Bykov (Mr), Innovative firm SNIIP Atom LLC
Models of Pin‐wise Reconstructions in VERONA System and its Validation by MIDI‐Core Benchmark
I. Pós (Dr), MVM Paks NPP
Investigation of circulating temperature fluctuations of the primary coolant in order to develop an enhanced MTC estimator for VVER‐440 reactors, Centre for Energy Research
S. Kiss (Dr), Hungarian Academy of Sciences
The verification results of Methodology for determining the weighted mean coolant temperature in the primary circuit hot legs of WWER‐1000 reactor plants
Consideration of influence of the gap size (between fuel assemblies) changes onto power field distribution in VVER‐1000 reactors with the help of PERMAK‐A code
A. Ryzhov (Mr), NRC "Kurchatov institute"
Shutdown margin calculations for the determination of the limiting position of control fuel assemblies on Dukovany NPP
M. Šašek (Dr), ŠKODA JS a.s.

Reactor dynamics and safety analysis

AER Working Group D on VVER Safety Analysis – Report of the 2016 Meeting
S. Kliem (Dr), HZDR
Apros Multipurpose Simulation Software for Improvement of Safety and Efficiency of VVERs
K. Porkholm (Mr), Fortum
Process of asymmetric boron dilution at VVER‐1000 of Kudankulam NPP during Fast Boron Injection System test: Experimental Results and Modelling
S.V. Tsyganov (Mr), NRC "Kurchatov institute"
BEPU approach for WWER safety analysis in RIA
I. Ovdiienko (Dr), SSTC N&RS
Start‐Up of Cold Loop, the 7th AER Benchmark Calculation with HEXTRAN‐ SMABRE‐PORFLO
V. Hovi (Mr), VTT
The procedures for searching conservative initial core states for some reactivity initiated accidents (RIA) taking into account xenon transients
S. Semenov (Mr), NRC "Kurchatov institute" disposal and actinide transmutation continues
Extension of Hybrid Micro‐Depletion Model for Decay Heat Calculation in DYN3D Code
Y. Bilodid (Dr), HZDR
Possible beyond design‐basis accident analysis dealing with crippling of VVER‐1200 fuel assemblies, Joint Institute for Power&Nuclear Research‐ Sosny
S. Polazau (Mr), National Academy of Science of Belarus
Performing pin‐by‐pin calculations in the frame of Kalinin‐3 benchmark
I. Pasichnyk (Dr), GRS gGmbH
A Methodology for the Estimation of the Radiological Consequences of a LOCA Event
A. Keresztúri (Mr), AEMI Nuclear Energy Engineering Office Company Limited
Monte Carlo calculation of Na‐24, K‐42 and N‐16 isotopes in the coolant of VVER‐440 nuclear reactors
G. Radócz (Mr), BME NTI
Recalculating the steady state conditions of the V‐1000 zero‐power facility at Kurchatov Institute using Monte Carlo and nodal diffusion
V. Sahlberg (Mr), VTT
Differential reactivity coefficients estimation method for VVER reactor by KORSAR/GP and TRAP‐KS codes application
M. Uvakin (Mr), JSC OKB Gidropress

Nuclear applications of computational fluid dynamics

CFD Analyses of the Rod Bowing Effect on the Subchannel Outlet Temperature Distribution
T. Toppila (Mr), Fortum
Experimental and numerical thermal‐hydraulics investigation of a molten salt reactor concept core
B. Yamaji (Mr), BME NTI
CFD analysis on the test section of SCWR‐FQT demo loop, Numerical Analysis on the Effect of Wrapped Wire Spacers on Thermal Hydraulics in a Four Rod Fuel Bundle
B. Mervay (Mr), BME NTI

Fuel behavior in normal conditions

Poolside Inspections of Spent Nuclear Fuel at Loviisa NPP
I‐V. Lehtinen (Mr), Fortum
Fuel Behavior Calculations for Developed Fuel and Cycle at Paks NPP, Hungary
G. Bóna (Mr), MVM Paks NPP
Current State of Fuel Performance Modelling in the Loviisa NPP
V. Peri (Mr), Fortum

Intermediate storage of spent fuel decommissioning and radwaste / Spent fuel disposal and actinide transmutation

AER Working Group E Activities in 2016, VUJE
R. Zajac (Dr), a.s
Assessment of the Reactivity Bias and Bias Uncertainty Due to WWEr‐440 Fuel Depletion Uncertainties
S. Bznuni (Dr), Nuclear and Radiation Safety Center
Simultaneous application of X‐ray fluorescence and gamma spectrometer for analysis of radioactive waste material topic
A. Gerényi (Ms), BME NTI
Source Term Determination for VVER‐440/V230 Reactor Decommissioning by MCNP5, Slovak University of Technology in Bratislava
M. Oravkin (Mr), Institute of Nuclear and Physical Engineering
Comparison of determined MCNP neutron source terms for VVER‐ 440/V230 decommisioning, Slovak University of Technology in Bratislava
K. Kristofova (Ms), Institute of Nuclear and Physical Engineering
Nuclear Criticality Safety Analysis of Wet Interim Storage Pool Using Mcnp5, Slovak University of Technology in Bratislava
G. Farkas (Mr), Institute of Nuclear and Physical Engineering
Development in Studsvik’s system for spent fuel analyses
T. Simeonov (Mr), Studsvik Scandpower Inc
Inventory of Spent Fuel VVER‐440 With Cooling Time up to 80 Years, VUJE
R. Zajac (Dr), a.s.
Study on the impact of transition from 3‐batch to 4‐batch loading at Loviisa NPP on the long‐term decay heat and activity inventory
T. Lahtinen (Mr), Fortum
Development of a source term related to the geological disposal of spent nuclear fuel in Slovakia
D. Barátová (Ms), Slovak University of Technology in Bratislava
Extention of Pool at the Reactor Analyses in Slovakia after Fukushima, VUJE
R. Zajac (Dr), a.s.
SCALE 6.2 ‐ verification for criticality, nuclide composition and decay heat calculation, VUJE
R. Zajac (Dr), a.s.

SERPENT workshop

Brief introduction to Serpent
J. Leppänen (Dr)
Methodology for spatial homogenization
J. Leppänen (Dr)
Multi‐physics capabilities of Serpent
V. Valtavirta (Mr)
The use of Serpent 2 with the nodal reactor analysis code TRAB3D at VTT
V. Sahlberg (Mr)
An overview of assembly leakage models in Serpent 2
E. Dorval (Dr)
Some multi‐physics applications of Serpent
V. Valtavirta (Mr)