Agenda for 28th Symposium of AER on VVER Reactor Physics and Reactor Safety
Monday
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) |
Tuesday
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) |
Wednesday
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) |
Thursday
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) |
lunch
Friday
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 |
lunch