Agenda for 29th Symposium of AER on VVER Reactor Physics and Reactor Safety

Track 1 -- advances in spectral and core calculation methods

VVER-440 BENCMARK WITH C-PORCA	Márton Horváth, István Pós, Sándor Patai Szabó
SOLUTION OF THE VVER-1000 FULL CORE CALCULATION BENCHMARK BY KARATE CODE SYSTEM	E. Temesvári, Gy. Hegyi, G. Hordósy and Cs. Maráczy
Radiation heating of VVER-440 thermocouple	Martin Lovecký, Jan Šik
Full-Core VVER-1000 calculation benchmark	Daniel Sprinzl, Václav Krýsl, Pavel Mikoláš, Jiří Závorka
THE CURRENT STATUS OF THE KASKAD SOFTWARE PACKAGE	A. A. Aleshin, A. P. Lazarenko, M. Ju. Tomilov
INFORMATION ON AER WG A ON IMPROVEMENT, EXTENSION AND VALIDATION OF PARAMETRIZED FEW-GROUP LIBRARIES FOR VVER 440 AND VVER 1000	Pavel Mikoláš
Solution of Full-Core VVER-440 PK-3+ calculation benchmark by Serpent	Jiří Závorka, Václav Krýsl, Pavel Mikoláš, Daniel Sprinzl
Calculations of neutron-physical characteristics of “Full-core” benchmark by programs TDMCC and Sapfir&RC	Frolova M.V., Antonov S.N., Ustinov A.N., Fateev M.V.
DEVELOPMENT OF PLANT SYSTEM THERMAL HYDRAULICS NEUTRONICS COMPUTER CODE ATMIKA LWR FOR KUDANKULAM VVER 1000 MWe REACTOR	Hemant Kalra, Sanjay Singh, Paresh Patra, Y.K. Pandey, G.Biswas

Track 2 -- reactor physics experiments and code validation

VALIDATION OF NEW CMS5-VVER NUCLEAR DATA LIBRARY USING CRITICAL EXPERIMENTS AND X2 FULL-CORE BENCHMARK	Rodolfo Ferrer and Tamer Bahadir
Application of advanced measurement method of CPS CR group worth for VVER unit	Xiaoqiang Yang, S.V. Tsyganov
Validation results of the BIPR-8A code, the new module of the software package KASKAD.	Soshitov N.P., Tomilov M.Y., Yasnopolskaya I.I.
CALCULATION OF THE TRANSITION FUNCTIONS OF SELF-POWERED DETECTORS FOR VVER-1000 BY MEANS OF THE MCU-PD AND TVS-M CODES	Bikeev A.S., Kurchenkov A.Yu., Shkarovsky D.A., Shkityr V.V.
The results of the certification of the code ATHLET/BIPR-VVER version 1.0	A. Kotsarev, M. Lizorkin, B. Shumskiy
Validation of Monte Carlo Activation Calculation for V1 NPP Reactor Concrete Shaft	Michal Šnírer, Kristína Krištofová, Gabriel Farkas, Vladimír Slugeň
NUMERICAL AND EXPERIMENTAL STUDY OF THE NATURAL CIRCULATION MODE DURING COMMISSIONING UNIT-1 NOVOVORONEZH NPP-2	Yu. Saunin, A. Dobrotvorski, D. Markin, A. Kotcarev, V. Egorov
ANALYSIS OF THE STARTUP PHYSICS TESTS OF A VVER-1200 REACTOR WITH THE KARATE-1200 CODE SYSTEM	E. Temesvári, Cs. Maráczy and Gy. Hegyi
PRELIMINARY MODELING OF THE PROCESS OF REGULATING GROUP INSERTION IN COURSE OF THE START-UP TEST OF TAINWAN-4	P.V. Gordienko1, A.V. Kotsarev1, I.G. Lomakin1, S.V. Tsyganov1, Xiaoqiang Yang2, Liusuo Ye2

Track 3 -- fuel management issues

Qualification of HELIOS models for XS preparations to new types of fuel	M. Ieremenko, Iu. Ovdiienko, Y. Bilodid
A new data processing tool for generating homogenized cross sections for the HEXBU-3D code	Tuukka Lahtinen, Jaakko Kuopanportti
OPTIMIZATION OF POWER MICROFIELD DISTRIBUTION IN JA-PROFILED RK3+ FUEL ASSEMBLIES WITH 4.68% AVERAGE ENRICHMENT FOR VVER-440 PROSPECTIVE FUEL CYCLES	A.A. Gagarinskiy, D.R. Kireeva, Zh.Yu. Liventseva, D.A. Oleksyuk
Neutron flux spectra comparison obtained with Serpent and SCALE for VVER-1000	A. Travleev, R. Henry, A. Aures
An Analysis of Criticality Achievement Process	J.Bajgl, M.Bárta
Cycle extension in Slovak VVER-440 reactors to 14 months	R. Zajac, J. Majerčík and C. Strmenský
AER WORKING GROUP B ACTIVITIES IN 2019	P. Dařílek
Status and plans of Paks NPP fuel management	I. Nemes

Track 4 -- core surveillance and monitoring

SAFETY ASSESSMENT CALCULATION PROCEDURE FOR OPERATING VVER UNIT IN MANEUVERING REGIMES EXPERIMENT	M.A.Uvakin, I.V.Makhin, A.L.Nikolaev, E.V.Sotskov
Time dependent leakage model to identify defective fuel assemblies in VVER-type nuclear reactors	Dr. Imre Szalóki, Gábor Radócz, Dr. Tamás Pintér, Péter Jakab Rozmanitz, Ilona Varjúné Baracska, Dr. Anita Gerényi
ICIS power density monitoring in high-power VVER NPP. Calculation and experimental justification of accuracy characteristics.	N.V. Lipin, N.V. Milto, D.N. Skorokhodov, A.Yu. Kurchenkov
SCORPIO-VVER Core Monitoring and Surveillance for VVER-440 NPPs	Jozef Molnár
WORKING GROUP C ACTIVITIES IN 2019	I. Nemes

Track 5 -- reactor dynamics and safety analysis

SKETCH-N/ATHLET steady-state and dynamic coupled scheme verification results on Kalinin-3 benchmark	V.I. Romanenko, V.G. Zimin, S.P. Nikonov, G.V. Tikhomirov, Y. Perin, R. Henry, K. Velkov
New Method of Power Maneuvering for NPPs with WWER and PWR	G.Ponomarenko, A.Rumik
Comparative analysis of ECCS calculation models in program complex KORSAR/GP	Latkin Dmitrii, PhD Petkevich Ivan
Maximum Pressure drop values in the main components of VVER-1000 due to DEBLOCA in different locations	Dina Ali Amer Ph.D. Student, National Research Nuclear University “MEPhI”, Moscow, Russia Teacher Assistant, Alexandria University, Egypt Dina.amer@alexu.edu.eg Nikonov S.P. NRNU “MEPhI”, Moscow, Russia SPNikonov@mephi.ru
Finite element solution of the time-dependent SP3 equations using an implicit integration scheme	Boglárka Babcsány, Tamás Bartók, Dániel Péter Kis
COMPARISON OF CALCULATION RESULTS OF TRANSIENTS IN THE VVER-1000 AND VVER-1200 CORES OBTAINED USING NOSTRA CODE WITH EXPERIMENTAL DATA	D. Afanasyev, A. Pinegin, S. Semenov, A. Ryzhov, NRC “Kurchatov institute”, Russian Federation
ESTIMATION OF REACTIVITY COEFFICIENTS OF VVER-1200 REACTORS ON THE BASIS OF MEASUREMENTS MADE AT POWER LEVELS	K. Gomozov, A. Pinegin, S. Semenov, A. Scheglov, NRC “Kurchatov institute”, Russian Federation
VVER TRANSIENT SIMULATION RESULTS ANALYSIS FOR MAIN STEAM LINE BREAK ACCIDENT USING FUEL ASSEMBLY PIN-BY-PIN MODEL BY KORSAR/GP CODE	Sinegribova A.I., Uvakin M.A.
AER WORKING GROUP D ON VVER SAFETY ANALYSIS – REPORT OF THE 2019 MEETING	S. Kliem
TRANSIENT ANALYSIS OF A DETAILED THERMAL-HYDRAULIC MODEL OF A VVER-1000 CORE WITH THE SYSTEM CODE ATHLET	R. Henry, Y. Périn, K. Velkov, S.P. Nikonov
RELAP5-3D© REACTOR CORE MODEL FOR VVER1000/320 WITH NEUTRONIC XS DATA IN GEN FORMAT	J. Hádek, M. Benčík

Track 6 -- nuclear applications of computational fluid dynamics (CFD)

Simulation of Subcooled Boiling in Multiphase CFD Code CFX	Ladislav Vyskočil, Václav Železný and Pavel Zácha
CFD CALCULATIONS FOR L-STAR EXPERIMENTAL GAS COOLED SYSTEM	G. I. Orosz, S. Tóth, A. Aszódi
Overview of AER Working Group G activities	Bogdán Yamaji
SIMULATION OF CROSSFLOWS IN A MIXED CORE OF VVER REACTOR WITH SUBCHANNEL CODE AND CFD CODE	Vít Doleček1*, Ladislav Vyskočil1 and Václav Železný1,2

Track 7 -- spent fuel disposal and actinide transmutation

ANALYSIS OF CORIUM CRITICALITY IN VVER-440 DURING SEVERE ACCIDENT	Ievgen Bilodid, Olena Dudka, Yuri Kovbasenko
CRITICALITY SAFETY ANALYSIS OF SPENT FUEL STORAGE POOL FOR NPP MOCHOVCE	K. Kaprinayova, G. Farkas, K. Kristofova, P. Hausner, V. Slugen
SIMPLIFIED CRITICALITY SAFETY CALCULATIONS OF SPENT FUEL STORAGE POOL	Peter Hausner, Gabriel Farkas, Katarína Kaprinayová, Kristína Krištofová, Vladimír Slugeň
UNCERTAINTIES ASSOCIATED WITH NUCLEAR DATA WHEN CALCULATING FUEL ISOTOPE CONCENTRATIONS AT BURNUP	Pavel Mikoláš
Preliminary results of a model of impurities and activation of STUDSVIK's SNF code	Teodosi Simeonov
OVERVIEW OF AER WORKING GROUP E ACTIVITIES IN 2019	R. Zajac
SERPENT VALIDATION AT EXPERIMENTAL FAST SPECTRUM	P. DAŘÍLEK, R. ZAJAC

Track 8 -- Nuclear Fuel Cycle Perspectives and Sustainability

AER WORKING GROUP F ACTIVITIES IN 2019	Pavel N. Alekseev, Victor Yu. Blandinskiy, Anatoly A. Dudnikov

Track 9 -- Openning

Opennig	Radoslav ZAJAC

Track 10 -- Symposium 2020

Welcome to 30th Symposium of AER in Russia	A. Kotsarev

Track 11 -- Common Photos, AER 2019

Common Photo 1	Radoslav ZAJAC
Common Photo 2	Radoslav ZAJAC
Common Photo 3	Radoslav ZAJAC
Common Photo 4	Radoslav ZAJAC
Common Photo 5	Radoslav ZAJAC