Agenda for 28th Symposium of AER on VVER Reactor Physics and Reactor Safety


Session 1.1 (Symposium welcome)
9:00 9:25 1.01 Welcome address UJV
Session 2.1 (Advances in spectral and core calculation methods) chair: Chuck Wemple
9:25 9:50 2.01 Information on AER WG A on improvement, extension and validation of parametrized few-group libraries for VVER 440 and VVER 1000 Pavel Mikoláš (SKODA JS)
9:50 10:15 2.02 Development of CASMO5 for VVER-1000 analysis and preliminary validation using critical experiments Rodolfo M. Ferrer, Joshua M. Hykes, Joel D. Rhodes (Studsvik Scandpower)
10:15 10:40 2.03 Extension of nodal diffusion solver of Ants to hexagonal geometry Antti Rintala, Ville Sahlberg (VTT)
coffee break
Session 2.2 (Advances in spectral and core calculation methods) chair: Pavel Mikolas
11:05 11:30 2.04 ACMFD formulation of the HEXNEM3 method for solving the time-dependent neutron diffusion equation via modal decomposition Srebrin Kolev, Ivaylo Christoskov (Sofia University)
11:30 11:55 2.09 Complex modeling of VVER-1000 fuel assembly using codes MCU/ATHLET with different hydraulic models V. I. Romanenko, S. P. Nikonov, G. V. Tikhomirov (MEPhI)
11:55 12:20 2.06 Adaptation of the gas gap simplified model in DYN3D code to new types of fuel M.Ieremenko, Iu.Ovdiienko (SSTC NRS)
lunch break
Session 3.1 (Reactor physics experiments and code validation (benchmarks)) chair: Daniel Sprinzl
13:40 14:05 3.04 Experience of HELHEX code package validation at Kozloduy NPP Aleksandar Kamenov, Krasimir Kamenov (Kozloduy NPP)
14:05 14:30 3.01 'FULLCORE' and 'MIDICORE' VVER-1000 Benchmark Evaluations with Studsvik's CMS5-VVER Codes Tamer Bahadir, Emiliya Georgieva (Studsvik)
14:30 14:55 3.02 VVER-1000 Fuel Assembly Model in CAD-Based Unstructured Mesh for MCNP6 Martin Lovecký, Jiří Závorka, Jan Vimpel (ŠKODA JS)
coffee break
Session 4.1 (Fuel management issues) chair: Yuri Kukushkin
15:20 15:45 4.01 AER working group B activities in 2018 Petr Dařílek (VUJE)
15:45 16:10 4.02 New fuel of the third-plus-generation with modified JA-profile enrichment for VVER-440. Perspective 15 monthly fuel cycles for VVER-440. Zh. Liventseva, A. Gagarinsky (NRC Kurchatov Institute)
16:10 16:35 4.03 Prospective 18-month fuel cycles for VVER-440:advantages of new uranium-erbium fuel assemblies A. Gagarinskiy, E. Osipova (NRC Kurchatov Institute)
16:35 17:00 4.04 Core Loading Optimization in Slovak VVER-440 Reactors R. Zajac, M. Majerčík (VÚJE)


Session 5.1 (Core surveillance and monitoring) chair: Josef Molnar
9:00 9:25 5.01 In-Core Monitoring of AES-2006: Design Basis and Characteristics A. Е. Kalinushkin, Yu.М. Semchenkov, N.V. Milto (NRC Kurchatov Institute)
9:25 9:50 5.02 Statistical evaluation of c15 fuel cycles in Paks NPP based on measured in-core data Márton Horváth, István Pós, Tamás Parkó (Paks NPP)
9:50 10:15 5.03 Full-scale tests of ICMS for VVER-1200 during commissioning Novovoronezh NPP-2 unit-1: features and results related to the coolant temperature monitoring at a core entrance Iu. Saunin, A. Dobrotvorski, A. Semenikhin, R. Zubcov, S. Ryasny (JSC Atomtechenergo)
10:15 10:40 5.04 A storage of ICIS historical data at the NRC «Kurchatov institute». Potential and perspectives M.V. Khalizov, O.I. Sinegub, I.A. Eliseev, D.V. Vorobyeva (NRC Kurchatov institute)
coffee break
Session 6.1 (Reactor dynamics and safety analysis) chair: Ievgen Bilodid
11:05 11:30 6.01 AER working group D on VVER safety analysis – report of the 2018 meeting S. Kliem (HZDR)
11:30 11:55 6.02 LOCA and pressure waves in the primary circuit of the reactor VVER-1000 Dina Ali Amer (TA Alexandria University, PhD. student NRNU MEPHI, Moscow), S. P. Nikonov (NRNU MEPHI, Moscow)
11:55 12:20 6.03 Comparative thermohydraulic analyses of VVER 1000 active core for two different assembly construction types Perin Y., Nikonov S.P., Henry R., Pasichnyk I., Velkov K. (GRS)
lunch break
Session 7.1 (Nuclear applications of computational fluid dynamics (CFD))
13:40 14:05 7.01 Prediction of the Departure from Nucleate Boiling with CFD Code Ladislav Vyskočil, Václav Železný (ÚJV Řež)
Session 8.1 (Spent fuel disposal and actinide transmutation) chair: Jaakko Kuopanportti
14:05 14:30 8.01 Summary of activites of WG E on spent fuel R. Zajac (VUJE)
14:30 14:55 8.02 Summary of 19th session of the AER Working Group F «Nuclear Fuel Cycle Prospective and Sustainability» Blandinskiy V., Dudnikov A. (NRC Kurchatov Institute)
14:55 15:20 8.03 A procedure for verification of STUDSVIK's Spent Nuclear Fuel code Teodosi Simeonov (Studsvik Scandpower)
coffee break
Session 8.2 (Spent fuel disposal and actinide transmutation) chair: Radoslav Zajac
15:45 16:10 8.04 Applied study on optimizing the final disposal of Loviisa NPP spent fuel assemblies Tuukka Lahtinen, Jaakko Kuopanportti (Fortum)
16:10 16:35 8.05 Criticality Safety Analysis for GNS IQ - The Integrated Quiver System for Damaged Fuel Dr. M. Chernykh, D. Amian, Dr. S. Tittelbach, Dr. A. Bannani, W. Cebula, Dr. T. Funke and R. Hüggenberg (GNS)
16:35 17:00 8.06 Neutron balance in two-component nuclear energy system V. Blandinskiy (NRC Kurchatov Institute)


Session 9.1 (Other technical presentations) chair: Teodosi Simeonov
9:00 9:25 9.01 AER website and symposium organization software presentation F. Havlůj (NRI)
Session 2.3 (Advances in spectral and core calculation methods) chair: Teodosi Simeonov
9:25 9:50 2.08 SFullcore – framework for full-core VVER calculations using SERPENT M. Gren (NRI)
9:50 10:15 2.07 HELIOS and SERPENT validation at fast spectrum Petr Dařílek, Tomáš Chrebet, Radoslav Zajac (VUJE)
10:15 10:40 2.05 UANDREA – framework for evaluation of core physics uncertainties F. Havlůj (NRI)
coffee break
Session 2.4 (Advances in spectral and core calculation methods) chair: Frantisek Havluj
11:05 11:30 2.10 Group constant generation and core design optimization methodology for the GEN IV ALLEGRO reactor Bálint Batki, András Keresztúri, István Pataki, István Panka (MTA EK)
11:30 11:55 2.11 C-PORCA 7: a nodal diffusion reactor calculation code to support off-line and on-line core analysis at Paks nuclear power plant I. Pós, Z. Kálya, T. Parkó, M. Horváth (NPP Paks); S. P. Szabó (TS Enercon)
11:55 12:20 2.12 McSAFE - High Performance Monte Carlo Methods for Safety Demonstration V. Sánchez (KIT), L. Mercatali (KIT), F. Malvagi (CEA), P. Smith (AMEC), J. Dufek (KTH), M. Seidl ( Preussen Elektra ), L. Milisdorfer (CEZ), J. Leppanen (VTT), E. Hoogenboom (DNC), R. Vocka (NRI), S. Kliem (HZDR), P. Van Uffelen (JRC), N. Kerkar (EDF)
lunch break
Session 3.2 (Reactor physics experiments and code validation (benchmarks)) chair: Sergey Tsyganov
13:40 14:05 3.03 Analysis of criticality achievement process and obtained experience Josef Bajgl (Dukovany NPP)
14:05 14:30 3.05 Benchmark calculation on reactivity compensation initiated by dilution of boron acid in VVER-1000 primary circuit coolant by stepwise control rods group insertion O.Yu. Kavun, V.V. Semishin, V.O. Kavun, G.R. Pipchenko (SEC NRS)
14:30 14:55 3.06 HELIOS2 Verification and Benchmark Testing Charles Wemple, Teodosi Simeonov (Studsvik Scandpower)
coffee break
Session 4.2 (Fuel management issues) chair: Josef Bajgl
15:20 15:45 4.05 Strategy of nuclear fuel development for VVER NPP A.V Ugryumov, A.B. Dolgov, A.A. Shishkin, Yu.A. Kukushkin (JSC TVEL)
15:45 16:10 4.06 Prospects for implementation of VVER nuclear fuel enriched above 5 % Yu. Vergazov, A.V. Ugryumov, A.B. Dolgov, A.I. Shaulskaya (JSC TVEL); Yu.M. Semchenkov, E.K. Kosourov, A.I. Osadchiy, A.M. Pavlovichev (NRC «Kurchatov Institute»)
16:10 16:35 4.07 Optimized 18-month low-leakage core loadings for uprated VVER-1000 A. L. Egorov, E. K. Kosourov, A. M. Pavlovichev, M. A. Sumarokov, S. M. Zaritskiy - (NRC “Kurchatov Institute”, Moscow, Russia), A.S. Morozov - (Balakovo NPP, Balakovo, Russia)
16:35 17:00 4.08 Fuel cycles with PK-3+ FAs for VVER-440 reactors Pavel Mikoláš, Jan Vimpel (ŠKODA JS)


Session 6.2 (Reactor dynamics and safety analysis) chair: Alexander Kotsarev
9:00 9:25 6.04 Mathematical model for VVER reactor safety assessment calculations in load regulating regimes M.A. Uvakin, I.V. Makhin, E.V. Sotskov (GIDROPRESS)
9:25 9:50 6.05 Application field assessment of FA pin-by-pin model by KORSAR/GP code A.I. Sinegribova, M.A. Uvakin (JSC GIDROPRESS)
9:50 10:15 6.06 Leningrad NPP-2 start-up loss of power test and its simulation with use of KORSAR/GP code M.V. Suslov, I.G. Petkevich, M.A. Uvakin (Gidropress)
10:15 10:40 6.07 Analysis Associated with Uncontrolled Dilution of Boric Acid Concentration in the Reactor VVER-1000/320 Jan Hádek, Radim Meca (ÚJV Řež)
coffee break
Session 6.3 (Reactor dynamics and safety analysis) chair: Soeren Kliem
11:05 11:30 6.08 Severe accident in-vessel stage subcriticality evaluation A.V. Tikhomirov, S.N. Antonov, K.Yu. Kurakin, S.I. Pantyushin, A.V. Nikolaeva (JSC OKB "GIDROPRESS", Podolsk)
11:30 11:55 6.09 Analysis of melt criticality of VVER-1000 during severe accidents within X2 benchmark Ievgen Bilodid (SSTC NRS)
Session 3.3 (Reactor physics experiments and code validation (benchmarks))
11:55 12:20 3.07 Simulation of zero power tests carried out at Novovoronezh NPP-2 unit 1 using ATHLET/BIPR-VVER A.V. Baykov, A.V. Kotsarev, S.V. Tsyganov (NRC Kurchatov Institute)


Session 3.4 (Reactor physics experiments and code validation (benchmarks)) chair: Istvan Pos
9:00 9:25 3.08 Coupling of the neutron diffusion code SKETCH-N and the thermal-hydraulics system code ATHLET for VVER-1000 calculations Koppány Pázmán, Vyacheslav Gennadevich Zimin, Sergey Pavlovich Nikonov
9:25 9:50 3.09 Physical start-up tests calculations for Dukovany and Temelín NPP using MOBY-DICK macrocode M. Růčka, M. Šašek (ŠKODA JS)
9:50 10:15 3.10 Effective Dose Calculation in the VVER-440 Reactor Maintenance Area Filip Osuský, Branislav Vrban, Štefan Čerba, Jakub Lüley, Vladimír Nečas (Slovak University of Technology)
10:15 10:40 3.11 Criticality Safety Calculation of VVER-440 Core by SCALE System Branislav Vrban, Štefan Čerba, Jakub Lüley, Filip Osuský, Vladimír Nečas (Slovak University of Technology)
coffee break
Session 3.5 (Reactor physics experiments and code validation (benchmarks)) chair: Ivaylo Christoskov
11:05 11:30 3.12 ‘FULL-CORE’ VVER-1000 Calculation Benchmark D. Sprinzl, V. Krýsl, P. Mikoláš, J. Závorka, J. Vimpel (ŠKODA JS)
11:30 11:55 3.13 „FULL-CORE“ VVER-440 RK3+ calculation benchmark P. Mikoláš, J. Vimpel, J. Závorka (ŠKODA JS)
Session 1.2 (Symposium welcome)
11:55 12:20 1.02 Closing of the symposium UJV