Name: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)
Start: 2017-06-26T08:00:00+05:00
End: 2017-06-29T17:00:00+05:00
Location: Yekaterinburg

International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)

from Monday, 26 June 2017 (08:00) to Thursday, 29 June 2017 (17:00)

Monday, 26 June 2017
08:30
08:30 - 09:30
Room: Plenary Hall
Contributions

08:30 Opening Address by Director General, ROSATOM (by video message) - Alexey Likhachev (ROSATOM)

08:40 Opening Address by Director General, IAEA (by video message) - Yukiya Amano (IAEA)

08:50 Welcome Note by Conference General Chair - Vyacheslav Pershukov (ROSATOM)

09:00 Welcome Note by Conference General Co-Chair - Mikhail Chudakov (IAEA)

09:05 Welcome Note by Deputy Presidential Envoy in the Ural Federation District - Alexander Moiseev

09:15 Fast Reactor Development and International Cooperation (by Honorary General Chair) - Subhash Chander CHETAL (India)
09:30 Coffee Break
Coffee Break
09:30 - 10:00
10:00
10:00 - 11:30
Room: Plenary Hall
Contributions

10:00 Closed fuel cycle technologies based on fast reactors as the corner stone for sustainable development of nuclear power - Evgeny Adamov (Institution “ITC “PRORYV” Project)

10:30 Research, development and deployment of fast reactors and related fuel cycle in China - Donghui ZHANG (China)

11:00 Status of the French Fast Reactor Programme - Sylvestre Pivet (France)
11:30 Lunch Break
Lunch Break
11:30 - 13:00
13:00
13:00 - 15:00
Room: Room 1
Contributions

13:00 Advanced Design Features of MOX Fuelled Future Indian SFRs - Puthiyavinayagam Pillai (Indira Gandhi Centre for Atomic Research)

13:20 Overview of U.S. Fast Reactor Technology R&D Program - Heather Bell (U.S. Department of Energy)

13:40 Development of the new generation power unit with the BN-1200 reactor - Sergey Shepelev (JSC “Afrikantov OKBM”)

14:00 Advanced sodium-cooled fast reactor development regarding GIF safety design criteria - Hiroki Hayafune (JAEA)

14:20 Current status of GIF collaborations on sodium-cooled fast reactor system - Hiroki Hayafune (JAEA)

14:40 Feasibility of Burning Wave Fast Reactor Concept with Rotational Fuel Shuffling - Toru Obara (Tokyo Institute of Technology)
13:00 - 15:00
Room: Room 2
Contributions

13:00 USSR and Russian fast reactor operation through the example of the BN600 reactor operating experience and peculiarities of the new generation BN800 reactor power unit commissioning - Yuriy Nosov (Beloyarsk NPP)

13:20 Main R&D objectives and results for under-sodium inspection carriers – Example of the ASTRID matting exceptional inspection carrier. - Francois Baque (CEA)

13:40 Development of under sodium viewer for next generation sodium-cooled fast reactor - Kosuke Aizawa (Japan Atomic Energy Agency)

14:00 Manufacture, Installation and Adjustment of the BN-800 Reactor Plant Equipment - Igor Petrov (JSC “Afrikantov OKBM”)

14:20 Testing and Qualification of Trailing Cable system for Prototype Fast Breeder Reactor - RAGHUPATHY S. (Indira Gandhi Centre for Atomic Research, Kalpakkam)

14:40 Safety Upgradation of Fast Breeder Test Reactor - Suresh Kumar K V (Department of Atomic Energy, India, Indira Gandhi Centre for Atomic Reaserch, Kalpakkam, Reactor facilities Group)
13:00 - 15:00
Room: Room 3
Contributions

13:00 The Status of Safety Research in the Field of Sodium-cooled Fast Reactors in Japan - Koji Morita (Kyushu University)

13:20 RECENT ACTIVITIES OF THE SAFETY AND OPERATION PROJECT OF THE SODIUM-COOLED FAST REACTOR IN THE GENERATION IV INTERNATIONAL FORUM - Alfredo Vasile (CEA)

13:40 “ASTRID safety design: Radiological confinement improvements compared to previous SFRs” - Stéphane BEILS (AREVA NP)

14:00 Safety Assurance for BN-1200 Power Unit During Accidents - Artem Anfimov (Joint Stock Company "Afrikantov Experimental Design Bureau for Mechanical Engineering")

14:20 The SAIGA experimental program to support the ASTRID Core Assessment in Severe Accident Conditions - Frédéric Payot (CEA : Commissariat à l’Energie Atomique et aux Energies Alternatives)

14:40 Study on Safety Design Concept for future Sodium-cooled Fast Reactors in Japan - Shigenobu Kubo (Japan Atomic Energy Agency)
13:00 - 15:00
Room: Room 5
Contributions

13:00 Fabrication Characteristics of Injection-cast Metallic Fuels - Jeong-Yong Park (Korea Atomic Energy Research Institute)

13:20 Metal fuel for fast reactors, a new concept - Boris Tarasov (NRNU MEPHI)

13:40 Development of innovative fast reactor nitride fuel in Russian Federation: state-of-art. - Liudmila Zabudko (Innovative &Technology Center by "PRORYV" Project)

14:00 Conceptual design of fuel and radial shielding sub-assemblies for ASTRID - Victor BLANC (CEA)

14:20 Development of Electromagnetic Devices for Sodium Cooled Fast Reactor Application - B.K. Nashine (Indira Gandhi Centre for Atomic Research, Kalpakkam (T.N.) - India)

14:40 Fuel Cladding Chemical Interaction Tests of Irradiated Metallic Fuel - Ju-Seong Kim (Korea atomic energy research institute)
13:00 - 15:00
Room: Room 6
Contributions

13:00 Numerical simulation of hydraulics and heat transfer in the BREST-OD-300 LFR fuel assembly - Dmitry Fomichev (JSC NIKIET)

13:20 Steady State Modelling and Validation of Once Through Steam Generator - Velusamy Karuppanna Gounder (Indira Gandhi Centre for Atomic Research)

13:40 Applications of the DNS CONV-3D Сode for Simulations of Liquid Metal Flows - Vladimir Chudanov (Nuclear Safety Insitute RAS (IBRAE))

14:00 3D Modeling of Fuel Handling System for PFBR Operator Training Simulator - Venkatesan Arasappan (Indira Gandhi Centre for Atomic Research)

14:20 Numerical Simulation Method of Thermal Hydraulics in Wire-wrapped Fuel Pin Bundle of Sodium-cooled Fast Reactor - Hiroyuki Ohshima (Japan Atomic Energy Agency)

14:40 Modelling and Simulation of Heat Transport System and Steam Power Transition System of CEFR - Zhao-Fei TIAN (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University)
13:00 - 15:00
Room: Room 4
Contributions

13:00 Current Status of Next Generation Fast Reactor Core & Fuel Design and Related R&D in Japan - Seiichiro Maeda (Japan Atomic Energy Agency)

13:20 Assessment of a nuclear energy system based on the integral indicator of sustainable development - Vladimir Usanov (JSC «SSC RF-IPPE», State Corporation “ROSATOM”)

13:40 Performance and sustainability assessment of nuclear energy deployment scenarios with fast reactors: advanced tools and application - Andrei Andrianov (National Research Nuclear University, MEPhI)

14:00 Comparison of Innovative Nuclear Energy Systems Based on Selected Key Indicators and Their Weighing Factors - Alexander Yegorov (researcher of Laboratory of Nuclear Fuel Cycle system analysis taking into account National and International tendencies)

14:40 Evaluation results of BN-1200 compliance with the requirements of GENERATION IV and INPRO - Elena Marova (JSC “Afrikantov OKBM”)
15:00 Coffee Break
Coffee Break
15:00 - 15:10
15:10
15:10 - 17:10
Room: Room 1
Contributions

15:10 Progress of Design and related Researches of Sodium-cooled Fast Reactor in Japan - Hideki Kamide (Japan Atomic Enery Agency)

15:50 Lessons and strategies from PFBR to Future Fast Breeder Reactors - Rajan Babu Vinayagamoorthy (Director (Technical))

16:10 Status of ASTRID Nuclear Island Design and Future Trends - JEAN-MARIE HAMY (AREVA NP)

16:30 Analysis of the Characteristics of the Fast Breeder Reactor with Metallic Fuel - IURII DROBYSHEV (VNIIAES JSC)

16:50 FASTER Test Reactor Preconceptual Design - Christopher Grandy (Argonne National Laboratory)
15:10 - 17:10
Room: Room 3
Contributions

15:10 Status of severe accident studies at the end of the conceptual design: feedback on mitigation features - Frédéric BERTRAND (CEA Cadarache)

15:30 Source Term Estimation for Radioactivity Release under Severe Accident Scenarios in Sodium cooled Fast Reactors - Vladimir Kriventsev (IAEA)

15:50 Advances in the Development of the SAS4A Code Metallic Fuel Models for the Analysis of PGSFR Postulated Severe Accidents - Seok-Hun Kang (KAERI)

16:10 Computational modeling of flow blockage in fuel subassemblies and molten material relocation in sodium cooled fast reactors - Velusamy Karuppanna Gounder (IGCAR)

16:30 Quantitative Evaluation of the Post Disassembly Energetics of a Hypothetical Core Disruptive Accident in a Sodium Cooled Fast Reactor - Barbara Vezzoni (Karlsruhe Institute of Technology (KIT)) MIchael Flad (Karlsruhe Institute of Technology)

16:50 An assessment of transient over-power accident in the PGSFR - KWI LIM LEE (KAERI)
15:10 - 17:10
Room: Room 4
Contributions

15:10 1992-2017: 25 years of success story for the Development of Minor Actinides Partitioning Processes - Christophe POINSSOT (French Nuclear and Alternative Energy Commission)

15:30 Comparison of fast reactors performance in the closed U-Pu and Th-U cycle - Jiri Krepel (Paul Scherrer Institut)

15:50 Reprocessing of fast reactors mixed U-Pu used nuclear fuel: studies and industrial test - Andrei Shadrin (Bochvar Institute)

16:10 Overview of the Nuclear Energy Agency Scientific Activities on Advanced Fuel Cycles - Stéphanie Cornet (Nuclear Energy Agency)

16:30 Assessment of the anticipated improvement of the environmental footprint of future nuclear energy systems - Christophe POINSSOT (French Nuclear and Alternative Energy Commission)

16:50 Concurrent Trends in Indian Fast Reactor Fuel Reprocessing Programme - KODANDARAMAN J (INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)
15:10 - 17:10
Room: Room 5
Contributions

15:10 The IAEA Coordinated Research Project on Sodium Properties and Safe Operation of Experimental Facilities in Support of the Development and Deployment of Sodium-cooled Fast Reactors (NAPRO) - E. Vázquez (National Atomic Energy Commission of Argentina (CNEA)) Osvaldo Azpitarte (National Atomic Energy Commission of Argentina (CNEA))

15:30 Effects of Oxygen Partial Pressure During Sintering at Laboratory and Industrial Scales on FR MOX Fuels - Stephane Vaudez (CEA)

15:50 Fuel Melting Margin Assessment of Fast Reactor Oxide Fuel Pins using a Statistical Approach - Victor BLANC (CEA)

16:10 New catalog on (U,Pu)O2 properties for fast reactors and first measurements on irradiated and non-irradiated fuels within the ESNII+ project - Kamil Tucek (European Commission, Joint Research Centre)

16:30 Fission product and swelling behaviour in FBTR mixed carbide fuel - Suresh Kumar Kannankara Vasudevan (IGCAR, Dept. of Atomic Energy, India)

16:50 Analysis of experimental data on fission gas release and swelling in mononitride fuel irradiated in BR-10 reactor - Sergey Porollo (IPPE)
15:10 - 17:10
Room: Room 2
Contributions

15:15 IAEA’s Coordinated Research Project on EBR-II Shutdown Heat Removal Tests: An Overview - Vladimir Kriventsev (IAEA)

15:25 EBR-II Passive Safety Demonstration Tests Benchmark Analyses - Laural Briggs (Argonne National Laboratory)

15:45 IAEA NEUTRONICS BENCHMARK FOR EBR-II SHRT-45R - Barbara Vezzoni (Karlsruhe Institute of Technology (Germany)) Wilfred Van Rooijen (Research Institute of Nuclear Engineering (RINE), University of Fukui, (Japan))

16:05 Conclusions of a Benchmark Study on the EBR-II SHRT-45R Experiment - Dalin Zhang (Xi'an Jiaotong University) Ethan Bates (TerraPower)

16:25 Thermal Hydraulic Investigation of EBR-II Instrumented Subassemblies during SHRT-17 and SHRT-45R Tests - Partha Sarathy UPPALA (Indira Gandhi Centre for Atomic Research)

16:45 Final Results and Lessons Learned from EBR-II SHRT-17 Benchmark Simulations - Nikita Rtishchev (IBRAE RAN)
15:10 - 17:10
Room: Room 6
Contributions

15:10 Thermal Hydraulic Study of Steam Generator of PGSFR - Jonggan Hong (KAERI)

15:30 EFFECT OF INLET TEMPERATURE AND OPERATING LINEAR HEAT RATING (LHR) ON THE MAXIMUM ACHIEVABLE BURNUP OF MK-1 CARBIDE FUEL IN FBTR - CLEMENT RAVI CHANDAR SOWRINATHAN (IGCAR, INDIA)

15:50 Extension to Heavy Liquid Metal coolants of the validation database of the ANTEO+ sub-channel code - Francesco Lodi (University of Bologna)

16:10 Density of sodium along the Liquid-Vapor Coexistence Curve, including the Critical Point - M. Laura Japas (CNEA - Argentina)

16:30 Experimental investigations of velocity and temperature fields, stratification phenomena in a integral water model of fast reactor in the steady state forced circulation - Aleksandr Trufanov (SSC RF-IPPE)

16:50 Development and Validation of Multi-scale Thermal-Hydraulics Calculation Schemes for SFR Applications at CEA - Yannick Gorsse (CEA-Saclay)
17:10 Coffee Break
Coffee Break
17:10 - 17:30
17:30
17:30 - 19:00
Contributions

17:35 The Safety Design Criteria Development and Summary of Its Update for the Generation-IV SFR Systems (USA/Japan/GIF) - Yasushi OKANO (Japan Atomic Energy Agency)

17:45 The Safety Design Guideline Development for Generation-IV SFR Systems (Japan/GIF) - Ryodai Nakai (Japan Atomic Energy Agency)

17:55 Considerations on GEN IV safety goals and how to implement them in future Sodium-cooled Fast Reactors (France) - Paul Gauthé (CEA)

18:05 Safety criteria for future Indian SFRs (India) - Subhash Chander CHETAL (India)

18:15 Compliance of Korean SFR Safety Design Approaches with Generation-IV Safety Design Criteria (Korea, R. of) - JAEWOON YOO (Korea Atomic Energy Research Institute)

18:25 Russian SFR Safety Requirements and Approaches and Their Correspondence to Generation-IV SFR Safety Design Criteria (Russia) - Iurii Ashurko (IPPE)

18:35 Panel Discussion
Tuesday, 27 June 2017
08:00
08:00 - 10:00
Room: Plenary Hall
Contributions

08:00 Indian Fast Reactor Programme : Status and R&D Achievements - ARUN KUMAR BHADURI (INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)

08:30 Current status and future view of the fast reactor cycle technology development in Japan - Yutaka Sagayama (Japan Atomic Energy Agency)

09:00 Status of Sodium Cooled Fast Reactor Development Program in Korea - JAEWOON YOO (Korea Atomic Energy Research Institute)

09:30 Research and Pilot Fast Neutron Reactors in Russian Federation as the Ground for Development of Worldwide Commercial Technologies - Alexander Tuzov (JSC "SSC RIAR")
10:00 Coffee Break
Coffee Break
10:00 - 10:20
10:20
10:20 - 12:00
Room: Room 1
Contributions

10:20 EXPERIMENTAL SEISMIC QUALIFICATION OF DIVERSE SAFETY ROD AND ITS DRIVE MECHANISM OF PROTOTYPE FAST BREEDER REACTOR - RAGHUPATHY S. (Indira Gandhi Centre for Atomic Research, Kalpakkam)

10:40 Progress in the ASTRID Gas Power Conversion System development - david plancq (CEA)

11:00 ASTRID FUEL HANDLING ROUTE FOR THE BASIC DESIGN - FRANCK DECHELETTE (CEA)

11:20 COMPONENT HANDLING SYSTEM : PFBR AND BEYOND - RAGHUPATHY S. (IGCAR, KALPAKKAM)

11:40 Main operation procedures for ASTRID gas power conversion system - dominique barbier (CEA)
10:20 - 12:00
Room: Room 3
Contributions

11:00 Development of Smart Component Based Framework for Dynamic Reliability Analysis of Nuclear Safety Systems - Puthiyavinayagam Pillai (Indira Gandhi Centre for Atomic Research)

11:20 Dynamic probabilistic risk assessment at a design stage for a sodium fast reactor. - VALENTIN RYCHKOV (EDF R&D)

11:40 PROBABILISTIC SAFETY ANALYSIS RESULTS FOR BN REACTOR POWER UNITS - Pavel Antipin (JSC “Afrikantov OKBM”)
10:20 - 12:00
Room: Room 5
Contributions

10:20 Development of core and structural materials for fast reactors - Tai Asayama (Japan Atomic Energy Agency)

10:40 Results of monitoring, using high-resolution neutron diffraction, of radiation-induced damages in claddings of fuel pins after their performance in the reactor BN-600 as a ground for prolongation of their life expectancy - Vladimir Bobrovskii (M.N. Miheev Institute of Metal Physics of Ural Branch of Russian Academy of Sciences)

11:00 FRACTURE STRAIN AND FRACTURE TOUGHNESS PREDICTION FOR IRRADIATED AUSTENITIC STEELS OVER WIDE RANGE OF TEMPERATURES TAKING INTO ACCOUNT THE EFFECT OF SWELLING AND THERMAL AGEING - Alexander Sorokin (Central Research Institute of Structural Materials “Prometey”)

11:20 IAEA activities in the area of Nuclear Power Reactor Fuel Engineering - Mikhail Veshchunov (IAEA)

11:40 Examination of Fast Reactor Materials and Structural Elements at JSC “INM” Premises - Alexander Kozlov (Joint Stock Company "Institute of Nuclear Materials")
10:20 - 12:00
Room: Room 2
Contributions

10:20 U.S. Sodium Fast Reactor Codes and Methods: Current Capabilities and Path Forward - Acacia Brunett (Argonne National Laboratory)

10:40 Validation of Advanced Metallic Fuel Models of SAS4A using TREAT M-Series Overpower Test Simulations - Aydin Karahan (Argonne National Laboratory)

11:00 Review of Transient Testing of Fast Reactor Fuels in the Transient REActor Test Facility (TREAT) - Colby Jensen (Idaho National Laboratory)

11:20 USDOE NEAMS Program and SHARP Multi-Physics ToolKit for High-Fidelity SFR Core Design and Analysis - Tanju Sofu (Argonne National Laboratory)
10:20 - 12:00
Room: Room 6
Contributions

10:20 The APOLLO3 scientific tool for SFR neutronic characterization: current achievements and perspectives - Gerald Rimpault (CEA)

10:40 INTEGRAL EXPERIMENTS WITH MINOR ACTINIDES AT THE BFS CRITICAL FACILITIES: STATE-OF-THE-ART SURVEY, REEVALUATION AND APPLICATION - Olga Andrianova (IPPE JSC “SSC RF –IPPE”, 1, Bondarenko sq., Obninsk, Kaluga reg. 249033)

11:00 International research center based on MBIR reactor – cornerstone for Generation 4 technologies development - Vyacheslav Pershukov (ROSATOM)

11:20 Verification of the neutron diffusion code AZNHEX by means of the Serpent-DYN3D and Serpent-PARCS solution of the OECD/NEA SFR Benchmark - Armando Miguel Gomez Torres (Instituto Nacional de Investigaciones Nucleares)

11:40 Benchmark Evaluation of Dounreay Prototype Fast Reactor Minor Actinide Depletion Measurements - Tatiana Ivanova (OECD Nuclear Energy Agency)
10:20 - 12:00
Room: Room 4
Contributions

10:20 Fast Reactors and Nuclear Cogeneration: A Market and Economic Analysis - Michele Frignani (ANN)

10:40 Providing the competitiveness of nuclear energy in the implementation of PRORYV project - Dmitriy Tolstoukhov (ITCP «PRORYV», Russian Federation)

11:00 COMPARATIVE ANALYSIS OF ELECTRICITY GENERATION FUEL COST COMPONENT AT NPPs WITH WWER AND BN-TYPE REACTOR FACILITIES - Viktor Dekusar (Laboratory of Nuclear Fuel Cycle system analysis taking into account National and International tendencies)

11:20 How to take into account the fleet composition in order to evaluate Fast Breeder Competitiveness - GILLES MATHONNIERE (CEA)

11:40 Equipment cost estimation for pilot demonstration lead-cooled fast-neutron reactor BREST-OD-300 - Nikolay Molokanov (ROSATOM, JSC “NIKIET”, MEPhI)
12:00 Lunch Break
Lunch Break
12:00 - 13:30
13:30
13:30 - 15:10
Room: Room 1
Contributions

13:30 SELECTION OF A LAYOUT FOR THE BN-800 REACTOR HYBRID CORE - Artem Kuznetsov (JSC “Afrikantov OKBM”)

13:50 ALLEGRO Core Neutron Physics Studies - Petr Dařílek (VUJE Inc., SK91864 Trnava, Slovak Republic)

14:10 BN-800 core with MOX fuel - Artem Kuznetsov (JSC “Afrikantov OKBM”)

14:30 Physics Investigation of a Supercritical CO2–cooled Micro-Modular Reactor (MMR) for Autonomous Load-Follow Operation - Hwan Yeal YU (KAIST)
13:30 - 15:10
Room: Room 3
Contributions

13:30 Numerical – experimental research in justification of fire (sodium) safety of sodium cooled fast reactors - Olga Myazdrikova (Leypunsky Institute for Physics and Power Engineering (IPPE))

13:50 Identification of important phenomena under sodium fire accidents based on PIRT process - Mitsuhiro Aoyagi (Japan Atomic Energy Agency)

14:10 Learning from 1970 and 1980-Era Sodium Fire Experiments - Luke Lebel (Institut de Radioprotection et de Sûreté Nucléaire)

14:30 SEISMIC SLOSHING EFFECTS IN LEAD-COOLED FAST REACTORS - Marti Jeltsov (KTH Royal Institute of Technology)

14:50 Evaluation of multiple primary coolant leakages accidents in Monju with consideration of passive safety features - Kazuo YOSHIMURA (Japan Atomic Energy Agency)
13:30 - 15:10
Room: Room 2
Contributions

13:30 PROBLEMS OF CALCULATION MODELLING OF NITRIDE FUEL PERFORMANCE: DRAKON CODE - Evgenii Marinenko (Institute for Physics and Power Engineering)

13:50 3D SIMULATION IN THE PLEIADES SOFTWARE ENVIRONMENT FOR SODIUM FAST REACTOR FUEL PIN BEHAVIOR UNDER IRRADIATION - bruno MICHEL (CEA/DEN/DEC/SESC/LSC)

14:10 Current status and progression of GERMINAL fuel performance code for SFR oxide fuel pins - Marc LAINET (French Alternative Energies and Atomic Energy Commission (CEA))

14:30 BERKUT – Best Estimate Code for Modelling of Fast Reactor Fuel Rod Behavior under Normal and Accidental Conditions - Andrey Boldyrev

14:50 EXPERIENCE AND APPLICABILITY OF HIGH DENSE METAL URANIUM IN ADVANCED BN-REACTORS - Iulian Golovchenko (Russian Federation)
13:30 - 15:10
Room: Room 5
Contributions

13:50 Modeling of Processes in Austenitic Steel Produced Under Irradiation in Fast Reactors and Possibilities of Model Practical Application - Alexander Kozlov (Joint Stock Company "Institute of Nuclear Materials")

14:10 Preliminary Inspection of Spent Fast Reactor Fuel Claddings - Vyacheslav Shikhalev (Joint Stock Company "Institute of Nuclear Materials")

14:30 OPERABILITY VALIDATION OF FUEL PINS WITH CLADDINGS MADE OF EK164-ID STEEL IN THE BN-600 REACTOR - Sergey Belov (JSC “Afrikantov OKBM”)

14:50 Creep resistance and fracture toughness of recently-developed optimized Grade 92 and its weldments for advanced fast reactors - Lizhen Tan (Oak Ridge National Laboratory)
13:30 - 15:10
Room: Room 6
Contributions

13:30 Stability Analysis of a Liquid Metal Cooled Fast Reactor - Branislav Vrban (B&J NUCLEAR ltd.)

13:50 Analysis of the BFS-115-1 experiments - Robert Jacqmin (CEA, Cadarache)

14:10 Physical start-up test of China Experimental Fast Reactor - Xingkai Huo (China Institute of Atomic Energy)

14:30 Neutronic evaluation of a GFR of 100 MWt with reprocessed fuel and thorium using SCALE 6.0 and MCNPX - Claubia Pereira (Universidade Federal de Minas Gerais)

14:50 Solution of the OECD/NEA SFR Benchmark with the Mexican neutron diffusion code AZNHEX - EDMUNDO DEL VALLE GALLEGOS (Instituto Nacional de Investigaciones Nucleares (On Sabbatical Leave from IPN-Mexico))
13:30 - 15:10
Room: Room 4
Contributions

13:30 Development and Deployment of Knowledge Management Portal for Fast Breeder Reactors - Venkatesan Arasappan (Indira Gandhi Centre for Atomic Research)

13:50 Topical issues of training of specialists for fast nuclear power engineering and the closed nuclear fuel cycle - Georgy Tikhomirov (NRNU MEPHI) Vyacheslav Pershukov (ROSATOM)

14:10 'EURATOM SUCCESS STORIES’ IN FACILITATING PAN-EUROPEAN E&T COLLABORATIVE EFFORTS - Roger GARBIL (European Commission Euratom Nuclear Fission)

14:30 GEN IV Education and Training Initiative via Public Webinars - Konstantin Mikityuk (Paul Scherrer Institute)

14:50 A proposal for a pan-European E&T programme supporting the development and deployment of ALFRED - Sara Bortot (KTH)
15:10 Coffee Break
Coffee Break
15:10 - 15:30
15:30
15:30 - 17:10
Room: Room 1
Contributions

15:30 Status of Generation-IV Lead Fast Reactor Activities - Alessandro Alemberti (Ansaldo Nucleare SpA)

15:50 Simplification, the atout of LFR-AS-200 - Luciano Cinotti (Hydromine Nuclear Energy S.a.r.l.)

16:10 Strategy and R&D status of China Lead-based Reactor - Qunying Huang (CnINEST)

16:30 BREST-OD-300 REACTOR FACILITY. DEVELOPMENT STAGES AND JUSTIFICATION - Vadim Lemekhov (JSC NIKIET)
15:30 - 17:10
Room: Room 5
Contributions

15:30 Experimental qualification of rotatable plug seals for Sodium Fast Reactor on a large scale test stand - karl vulliez (CEA, DEN, SDTC, Laboratoire d’Etanchéité, 30207, Bagnols Sur Cèze France.)

15:50 Heat Transfer Performance Test for a Sodium-to-Air Heat Exchanger with an Inclined Finned-Tube Banks - Hyungmo Kim (KAERI)

16:10 Development of the built-in primary sodium purification system for the - Sergey Rukhlin (JSC “Afrikantov OKBM”)

16:30 ASTRID French SFR: Progress in Sodium Gas Heat Exchanger development - david plancq (CEA)
15:30 - 17:10
Room: Room 6
Contributions

15:30 Recent and Potential Advances of the HGPT methodology - Augusto Gandini (Sapienza University of Rome)

15:50 Evaluation of βeff measurements from BERENICE programme with TRIPOLI4® and uncertainties quantification - Gerald Rimpault (CEA)

16:10 System of Codes and Nuclear Data for Neutronics Calculations of Fast Reactors and Uncertainty Estimation - Gennady Manturov (PhD)

16:30 Sensitivity and Uncertainty Analysis in Best-Estimate modeling for PGSFR Under ULOF Transient - Jaeseok Heo (Korea Atomic Energy Research Institute)

16:50 Objectives and Status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM) - Gerald Rimpault (CEA)
17:10 Coffee Break
Coffee Break
17:10 - 17:30
17:30
17:30 - 19:00
Room: Poster Area
Contributions

17:30 Neutronic Self-sustainability of a Breed-and-Burn Fast Reactor Using Super-Simple Fuel Recycling - Chihyung Kim (Korea Advanced Institute of Science and Techology)

17:30 A Preliminary Study of P&T Scenario on a Sustainable Energy System in China - Yong YANG (China Institute of Atomic Energy)

17:30 Fast Reactors - The Belgian Regulatory Approach - Matthias Vanderhaegen (Federal Agency for Nuclear Control)

17:30 Numerical Investigation of Sodium Spray Combustion Test with SPHINCS code - Takashi Takata (Japan Atomic Energy Agency)

17:30 Evaluation of Anticipated Transient without Scram for SM-SFR using SAS4A/SASSYS-1 - Deokjung Lee (Ulsan National Institute of Science and Technology)

17:30 Modeling technologies of fuel cycles - Inga Makeyeva (RFNC-VNIITF)

17:30 TRANSMUTATION TRAJECTORY ANALYSIS IN THE MODELLING OF LFR FUEL CYCLE - Mikołaj Oettingen (AGH University of Science and Technology, Faculty of Energy and Fuels, Department of Nuclear Energy)

17:30 Modeling of hydrodynamic processes at a large leak of water into sodium in the fast reactor coolant circuit - Olga Myazdrikova (Institute for Physics and Power Engineering named after A.I. Leypunsky” (IPPE))

17:30 The way of nitride fuel producing by high voltage electrodischarge compaction - Maria Tarasova (National research nuclear University "MEPhI")

17:30 SIBYLLA CODE: ASSESSMENT OF WATER BODIES CONTAMINATION AND DOSES RECEIVED BY POPULATION DUE TO RADIOACTIVITY DISCHARGES INTO THE HYDROSPHERE - Alexey Krylov (Nuclear Safety Institute of Russian Academy of Sciences)

17:30 Decay-heat removal in accidents in fast reactors with liquid metal coolant - IURII SHVETSOV (Private institution «Innovation and technology center for the «PRORYV» project»)

17:30 Use of ion irradiations to help design of advanced austenitic steels - Yann DE CARLAN (SRMA, CEA Saclay, Université Paris-Saclay, 91191 Gif-sur-Yvette Cedex, France)

17:30 Possibility studies of a boiling water cooled traveling wave reactor - Xue-Nong Chen (KIT, IKET)

17:30 Experience on MOX fuel fabrication for fast reactor at PFPF - Kiichi Suzuki (Japan Atomic Energy Agency)

17:30 Sensors of content of oxygen dissolved in heavy liquid metal coolants - Roman Sadovnichiy (JSC “SSC RF – IPPE”)

17:30 Isothermal transformation austenite-ferrite in a P92 steel - María Luppo (Argentina Atomic Energy Commission)

17:30 Precipitate phases in a weldment of P92 steel - María Luppo (Argentina Atomic Energy Commission)

17:30 Study of isolation valve for Sodium Fast Reactor - David Montagnier (AREVA NP) Dominique Villani (AREVA NP) Gilles Rodriguez (CEA) Julien Large (VELAN SAS) Marc Gosset (AREVA NP) Martin Delmas (VELAN SAS) Nicolas Crepin (VELAN SAS)

17:30 New results on the continuous cooling behavior of an ASTM A335 P92 steel - María Luppo (Argentina Atomic Energy Commission)

17:30 Study of the austenitization process in a P91 steel - María Luppo (Argentina Atomic Energy Commission)

17:30 Thermodynamics and separation factor of lanthanides and actinides in system “liquid metal-molten salt” - Valeri Smolenski (Institute of High-Temperature Electrochemistry UB RAS)

17:30 ECOLOGICAL ASPECTS OF THE USE OF FAST REACTORS IN A CLOSED NUCLEAR FUEL CYCLE UNDER THE “PRORYV” PROJECT - RUDOLF ALEXAKHIN (INSTITUTION «ITC «PRORYV» PROJECT»)

17:30 Investigations in a substantiation of high-temperature nuclear energy technology with fast-neutron reactor cooled by sodium for manufacture of hydrogen and other innovative applications - Aleksandr Sorokin (SSC RF-IPPE)

17:30 Preliminary transient analyses of SEALER - Ignas Mickus (LeadCold Reactors)

17:30 On the possibility of using various types of fuel in the MBIR reactor core - Pavel Maslov (SSC RF-IPPE)

17:30 The Effect of Proton Irradiation on the Corrosion Behaviors of Ferritic/Martensitic Steel - Jeonghyeon Lee (UNIST)

17:30 Thermal hydraulic investigation of sodium fire and hydrogen production in top shield enclosure of an FBR following a core disruptive accident - Velusamy Karuppanna Gounder (Indira Gandhi Centre for Atomic Research)

17:30 Numerical and Experimental Investigations of Tube-to-Tube Interaction of Air Heat Exchangers of PFBR under Seismic Excitations - Velusamy Karuppanna Gounder (Indira Gandhi Centre for Atomic Research)

17:30 Computational modelling of inter-wrapper flow and primary system temperature evolution in FBTR under extended Station Blackout - Velusamy Karuppanna Gounder (Indira Gandhi Center for Atomic Research)

17:30 Model validation of the ASTERIA-FBR code related to core expansion phase based on THINA experimental results - Tomoko Ishizu (Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R))

17:30 Multiscale computer modeling of nuclear fuel properties at radiation and thermal impacts - Sergey Starikov (Nuclear Safety Institute of the Russian Academy of Sciences)

17:30 The lead-cooled fast reactor transition to equilibrium operating conditions - Igor Volkov (Russian Federal Nuclear Center - All-Russia Research Institute of Technical Physics)

17:30 ROUZ CODE: CFD APPROACH FOR ASSESSMENT OF RADIATION SITUATION DURING ATMOSPHERE RADIOACTIVITY RELEASES WITHIN AN INDUSTRIAL SITE - Dmitry Blagodatskykh (Nuclear Safety Institute (IBRAE RAN))

17:30 Computational investigation of nuclear waste incineration efficiency in a subcritical molten salt driven by 50-100 MeV protons - Seyed Mohammad Mirvakili (AEOI) Zohreh Gholamzadeh (AEOI)

17:30 Optimization of the thermomechanical treatment to achieve a homogeneous microstructure in a 14Cr ODS steel - Benjamin Hary (CEA)

17:30 Resting Bottom Fast Reactor - Didier Costes (CEA)

17:30 The concept of 50-300 MWe modular-transportable nuclear power plant with sodium coolant and a gas turbine - Yurij Osheyko (none)

17:30 A High Density Uranium Zirconium Carbonitride LEU Fuel for Application in Fast Reactors - S Sikorin (The Joint Institute for Power and Nuclear Research SOSNY of the National Academy of Sciences of Belarus)

17:30 A Mechanistic Source Term Calculation for a Metal Fuel Sodium Fast Reactor - David Grabaskas (Argonne National Laboratory)

17:30 Advanced Reactor PSA Methodologies for System Reliability Analysis and Source Term Assessment - David Grabaskas (Argonne National Laboratory)

17:30 Advanced Energy Conversion for Sodium-Cooled Fast Reactors - James Sienicki (Argonne National Laboratory)

17:30 "Peculiarities of behavior of Coated Particle fuel in the core of Fast Gas Reactor BGR-1000" - Aleksei Sedov (NRC "Kurchatov Institute")

17:30 ASTRID hot cells - Bernard GUILLOU (SEIV)

17:30 Corrosion behavior of tube steel for BREST-OD-300 steam generator - Kirill Shutko (N.A. Dollezhal Research and Development Institute of Power Engineering)

17:30 ASTRID reactor: design overview and main innovative options for Basic Design - FREDERIC CHANTECLAIR (French Alternative Energies and Atomic Energy Commission (CEA))

17:30 The UO2– MeO2 (Me = Th, Pu, Zr) cathode crystalline deposits formation during the melts electrolysis. - Vladimir Krotov (Institute of High-Temperature Electrochemistry UB RAS)

17:30 3-D Core Design of the TRU-Incinerating Thorium RBWR Using Accident Tolerant Cladding - Sandra Bogetic (University of California at Berkeley)

17:30 Americium Retention During Metallic Fuel Fabrication - Randall Fielding (Idaho National Laboratory)

17:30 Study on the sensitivity analysis of the installed capacity and the high-level waste generation based on closed nuclear fuel cycle - Yun HU (China Institute of Atomic Energy)

17:30 THE CODE ROM FOR ASSESSMENT OF RADIATION SITUATION ON A REGIONAL SCALE DURING ATMOSPHERE RADIOACTIVITY RELEASES - Dmitry Dzama (Nuclear Safety Institute of Russian Academy of Science)

17:30 Full-fledged affination extractive-crystallizng platform for technology validation of the fast reactor spent fuel reprocessing on fast neutrons – the results of first experiments - Sergei Terentev (JOIN STOCK COMPANY «SIBERIAN GROUP OF CHEMICAL ENTERPRISES»)

17:30 SELECTION OF CARRIER SALT FOR MOLTEN SALT FAST REACTOR - Andrey Lizin (Russian Federation)

17:30 Examination of ChS-68 Steel Used as a BN-600 Reactor Cladding Material - Natalia Glushkova (Joint Stock Company «Institute of Nuclear Materials»)

17:30 X-RAY DIFFRACTION STRUCTURAL ANALYSIS OF STRUCTURAL AND FUEL MATERIALS FOR BN-600 REACTOR - Vladimir Tsygvintsev (Joint Stock Company “Institute of Nuclear Materials”)

17:30 Study on the limits of confinement leakage rates of pool-type sodium-cooled fast reactor - FENGLONG WANG (CHINA INSTITUTE OF ATOMIC ENERGY,BEIJING,CHINA)

17:30 (U,Pu)O2-x MOX pellet for Astrid reactor project - Thierry GERVAIS (AREVA)

17:30 The Commercial Potential of the Dual-Component Nuclear Power System - Mikhail Baryshnikov (Head of Back-End Departement)

17:30 Complex discussion of inherent safety fast reactors start-up with enriched uranium concept (strategical, economical aspects, problems of neutron physics etc.). R&D program proposal - Michael Orlov (Private institution «Innovation and technology center for the «PRORYV» project»)

17:30 Thermal conductivity of non-stoichiometric (Pu0.928Am0.072)O2-x - Taku Matsumoto (Japan Atomic Energy Agency)

17:30 A Conceptual design of engineering-scale plant applied the simplified MA-bearing fuel fabrication process - YOSHIKAZU YAMADA (Japan Atomic Energy Agency)

17:30 Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow - Konstantin Mikityuk (Paul Scherrer Institut)

17:30 Testing and Qualification of shielded flasks for handling sodium wetted large sized components of PFBR - Rajan Babu Vinayagamoothy (BHAVINI, Dept of Atomic Energy, Kalpakkam)

17:30 CHALLENGES DURING CONSTRUCTION OF SODIUM PIPING SYSTEMS FOR 500MWe PROTOTYPE FAST BREEDER REACTOR - Rajan Babu Vinayagamoorthy (Director (Technical))

17:30 The method of calculating tritium content in various technological media of BN-type reactors - Mikhail Kriachko (Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering named after A. I. Leypunsky")

17:30 ESFR-SMART: new Horizon-2020 project on SFR safety - Konstantin Mikityuk (Paul Scherrer Institut)

17:30 POSTREACTOR STATE OF THE STANDARD AND EXPERIMENTAL BN-600 FUEL KINDS - Evgenii Kinev (Institute of Nuclear Materials)

17:30 Benchmark Between EDF And IPPE On The Behavior Of Low Sodium Void Reactivity Effect Sodium Fast Reactor During An Unprotected Loss Of Flow Accident - David Lemasson (EDF)

17:30 Fabrication process of NpO2 pellets - Bangyue YIN (CIAE)

17:30 The behavior features of fuel elements with nitride fuel - theory and experiment - Igor Konovalov (National Research Nuclear University "MEPhI")

17:30 The core of the LFR-AS-200: robustness for safety - Giacomo Grasso (Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA))

17:30 Mechanical Design Evaluation of Fuel Assembly for PGSFR - Kyungho Yoon (Korea Atomic Energy Research Institute)

17:30 Design and Development of Stroke Limiting Device for Control & Safety Rod Drive Mechanisms (CSRDMs) of future FBRs - RAGHUPATHY S. (Indira Gandhi Centre for Atomic Research, Kalpakkam)

17:30 Main outcomes from the JASMIN project: development of ASTEC-Na for severe accident simulation in Na cooled fast reactors - NATHALIE GIRAULT (IRSN)

17:30 Passive Shutdown Systems for Liquid Metal-Cooled Fast Reactors - Staffan Qvist (LeadCold AB)

17:30 Assessment of accuracy from the use of point kinetics when analyzing transition processes in high power fast reactor - Igor Suslov (ITC "PRORYV" Project)

17:30 Overview of the U.S. DOE fast reactor fuel development program - William Carmack (Idaho National Laboratory)

17:30 Development of the U.S. Sodium Component Reliability Database - Matthew Denman (Sandia National Laboratories)

17:30 Code Qualification Plan for an Advanced Austenitic Stainless Steel, Alloy 709, for Sodium Fast Reactor Structural Applications - Krishnamurti Natesan (Argonne National Laboratory)

17:30 Controlling FCCI with Pd in metallic fuel - Michael Benson (Idaho National Laboratory)

17:30 Probabilistic Safety Analysis of NPP with BREST-OD-300 reactor - Mikhail Ivochkin (JSC NIKIET, MOSCOW/RUSSIA)

17:30 INSERTION RELIABILITY STUDIES FOR THE RBC-TYPE CONTROL RODS IN ASTRID - Denis Lorenzo (CEA)

17:30 Synergetic mechanism of high temperature radiation embrittlement of austenitic steels under long term neutron irradiation at high temperatures - Victoria Shvetsova (Central Research Institute of Structural Materials “Prometey”)

17:30 EVALUATION OF COBALT FREE COATINGS AS HARDFACING MATERIAL CANDIDATES IN SODIUM FAST REACTOR - FABIEN ROUILLARD (CEA)

17:30 Passive Complementary Safety Devices for ASTRID severe accident prevention - Edouard Bissen (CEA)

17:30 On-site nuclear fuel cycle of “BREST” reactors - Andrei Glazov (Institution “Innovation and Technology Center by “PRORYV” Project”, State Atomic Energy Corporation “Rosatom”)

17:30 BISON for Metallic Fuels Modeling - Christopher Matthews (Los Alamos National Laboratory)

17:30 IMPLEMENTATION STATUS OF CONTAIN-LMR SODIUM CHEMISTRY MODELS INTO MELCOR 2.1 - David Louie (Sandia National Laboratories)

17:30 OSCAR-Na validation against sodium loop experiments - Jean-Baptiste GENIN (CEA, DEN)

17:30 A Demand Driven Way of Thinking Nuclear Development – Neutron Physical Feasibility of a Reactor Directly Operating SNF from LWR - Bruno Merk (University of Liverpool)

17:30 On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors - Boris Hombourger (Paul Scherrer Institut (PSI), Switzerland; École Polytechnique Fédérale de Lausanne (EPFL), Switzerland)

17:30 Development of Fast Reactors in the USSR and the Russian Federation; Malfunctions and Incidents in the Course of their Operation and Solution of Problems. - Lev Kochetkov (Alexeevich)

17:30 Assessment of the reactivity effects of Gas cooled Fast Reactor - Jakub Lüley (Slovak University of Technology)

17:30 FACILITY FOR ADVANCED FUELS THROUGH THE SOL-GEL METHOD - Balija Sreenivasulu (IGCAR)

17:30 CHALLENGES IN THE FABRICATION AND RECYCLING OF MIXED CARBIDE FUEL - SUDHIR MISHRA (BHABHA ATOMIC RESEARCH CENTRE, INDIA)

17:30 Investigation of steel corrosion products mass transfer in sodium - Viktor Alekseev (JSC "SSC RF-IPPE")

17:30 The influence of porosity on thermal conductivity of low-density uranium oxide. - Kyoichi Morimoto (Japan Atomic Energy Agency)

17:30 Mechanical and Thermal Properties of (U,Pu)O2-x - Shun Hirooka (Japan Atomic Energy Agency)

17:30 Evaluation of irradiation-induced point defects migration during neutron irradiation in modified 316 stainless steel - Yoshihiro Sekio (Japan Atomic Energy Agency)

17:30 Remote detection of raised radioactivity in emission from Beloyarsk nuclear power plant - Gennady Kolotkov (V.E. Zuev Institute of Atmospheric Optics SB RAS)

17:30 Extending the grid plate life - Incorporation of lower axial shield for FBTR - Sureshkumar KV (RFG, IGCAR)

17:30 APPLICATION OF PHYSICAL MODELING WHEN CALIBRATING HIGH RANGE ELECTROMAGNETIC FLOWMETERS - Vadim Alexandrovich Shurupov (JSC “SSC RF – IPPE”)

17:30 DECAY HEAT REMOVAL SYSTEM IN THE SECONDARY CIRCUIT OF THE SODIUM-COOLED FAST REACTOR AND EVALUATION OF ITS CAPACITY - Iurii Ashurko (IPPE)

17:30 Structural Design and Evaluation of a Steam Generator in PGSFR - Chang-Gyu PARK (Korea Atomic Energy Research Institute)

17:30 VOIDING OF ELSY PRIMARY SYSTEM DURING STEAM GENERATOR LEAKAGE - Marti Jeltsov (KTH Royal Institute of Technology)

17:30 Modeling of Lanthanide Transport in Metallic Fuels: Recent Progresses - Cetin Unal (LANL)

17:30 Mathematical modeling of the mononitride nuclear fuel production processes - Igor Peshkichev (RFNC-VNIITF)

17:30 The study of U-232 accumulation in reprocessed uranium for fast reactor fuel cycle - Mikhail Kriachko (Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering named after A. I. Leypunsky")

17:30 Thermal and elastic properties of CexTh1-xO2 mixed oxides: a self-consistent thermodynamic approach - Anton Filanovich (Ural Federal University)

17:30 CORROSION OF 12X18H10T STEEL IN Ce-, Nd- AND U-CONTAINING MOLTEN LiCl-KCl EUTECTIC - Evgeniya Nikitina (Institute of High Temperature Electrochemistry)

17:30 ELECTRICAL CONDUCTIVITY OF MOLTEN LiCl-KCl EUTECTIC WITH COMPONENTS OF SPENT NUCLEAR FUEL - Alexander Salyulev (Institute of High Temperature Electrochemistry)

17:30 Change in Mechanical Properties of Spent Fast Reactor Claddings - Svetlana Barsanova (Joint Stock Company «Institute of Nuclear Materials»)

17:30 STATISTICAL INVESTIGATION OF RADIATION-INDUCED POROSITY IN BN FUEL CLADDINGS USING SCANNING ELECTRON MICROSCOPY - Vladimir Pastukhov (Joint Stock Company "Institute of Nuclear Materials")

17:30 An Assessment of Fission Product Scrubbing in Sodium Pools Following a Core Damage Event in a Sodium Cooled Fast Reactor - Matthew Bucknor (Argonne National Laboratory)

17:30 The Computer model for the economic assessment of NPP pilot demonstration energy complex with BREST-OD-300 reactor (REM Proryv Project) - Nikolay Molokanov (ROSATOM, JSC “NIKIET”, MEPhI)

17:30 CFD Simulation of Corium / Materials Interaction for Severe Accidents - Stéphane BEILS (AREVA NP)

17:30 Development of Ultra Sub-size Tensile Specimen for Evaluation of Tensile Properties of Irradiated Materials - Puthiyavinayagam Pillai (Indira Gandhi Centre for Atomic Research)

17:30 Preliminary Safety Performance Assessment of ESFR CONF-2 Sphere-pac‐Fueled Core - Sara Bortot (KTH)

17:30 Application of Heterogeneous Fuel Assemblies in the Core of Modular Fast Sodium Reactor - Yaroslav Kotov (National Recearch Centre "Kurchatov Institute")

17:30 Improving inherent safety BN-800 by the use of fuel assembly with (U, Pu)C microfuel. - Nikolay Maslov (National Research Centre "Kurchatov Institute" National Research Nuclear University MEPhI (Moscow Engineering Physics Institute))

17:30 Key features of design, manufacturing and implementation of laboratory and industrial equipment for Mixed Uranium – Plutonium Oxide (MOX) and Nitride fuel pellets fabrication in Russia - Alexander Denisov (Deputy Director International Business Sosny R&D Company) Vincent Reynaud (CHAMPALLE SAS)

17:30 Feasibility of MA Transmutation by (MA, Zr)Hx in Radial Blanket Region of Fast Reactor and Plan of Technology Development - Kazumi IKEDA (Mitsubishi FBR Systems, Inc.)

17:30 Towards a new approach for structural materials of Lead Fast Reactors - Pietro Agostini (ENEA)

17:30 The optimization of core characteristics of fast molten salt reactor based on neutron-physical and thermal-hydraulic calculations and the analysis of fuel cycle closure options - Mikhail Belonogov (RFNC-VNIITF named after academ. E.I. Zababakhin)

17:30 Impact of the irradiation of an ASTRID-type core during an ULOF with SIMMER-III - Sandra POUMEROULY (EDF R&D)

17:30 Tradeoff Study of Advanced Transmutation Fuels in Sodium-cooled Fast Reactors - Nicolas Stauff (Argonne National Laboratory)

17:30 High temperature design and evaluation of forced draft sodium-to-air heat exchanger in PGSFR - Nak Hyun Kim (Korea Atomic Energy Reasearch Institute)

17:30 Thermal Annealing Effect on Recovery of Corrosion Properties of EP-450 Steel Irradiated IN BN-600 Reactor to High Damage Doses - Oleg Golosov (Joint Stock Company "Institute of Nuclear Materials")

17:30 Investigation of Radiation-Induced Swelling of EK-164 Steel, an Advanced Material for BN-600 and BN-800 Claddings - Irina Portnykh (Joint Stock Company "Institute of Nuclear Materials")

17:30 Sodium compatibility of Recently-Developed Optimized Grade 92 and its Weldments for Advanced Fast Reactors - Meimei Li (Argonne National Lab)

17:30 FEATURES OF THE NUCLEAR FUEL CYCLE SYSTEMS BASED ON JOINT OPERATION OF FAST AND THERMAL REACTORS - Victor Dekusar (Dekusar)
Wednesday, 28 June 2017
08:00
08:00 - 10:00
Room: Plenary Hall
Contributions

08:00 The European Commission contribution to the development of safe and sustainable fast reactor systems - Jean-Paul Glatz (EC-JRC Karlsruhe)

08:30 Overview of GEN-IV International Forum Activities. Status and Prospects of Fast Reactors - Francois GAUCHE (GIF)

09:00 Overview of NEA Activities Related to Fast Reactors - Tatiana Ivanova (OECD Nuclear Energy Agency)

09:30 INPRO: Fast Reactors and Enhanced Nuclear Energy Sustainability - Jon Phillips (IAEA)
10:00 Coffee Break
Coffee Break
10:00 - 10:20
10:20
10:20 - 12:00
Room: Plenary Hall
Contributions

10:20 Feasibility and Challenges for Self-sustainable Long-Life SMR without Refueling - Yonghee Kim (Korea Advanced Institute of Science and Technology)

10:30 SVBR-100 as a possible option for developing countries, why? - Georgy Toshinsky (IPPE)

10:40 A safe and competitive lead-cooled small modular fast reactor concept for a short-term deployment - Giacomo Grasso (Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA))

10:50 Eligibility of Small Molten Salt Fast Reactor (S-MSFR) - Jiri Krepel (Paul Scherrer Institut)

11:00 Small fast reactors for arctic regions - Staffan Qvist (LeadCold AB)
12:00 Lunch Break
Lunch Break
12:00 - 13:30
13:30
13:30 - 15:10
Room: Room 1
Contributions

13:30 CORE CONDITON MONITORING IN ADVANCED COMMERCIAL SODIUM BN-1200 - Ivan Zverev (JSC “Afrikantov OKBM”)

13:50 The ASTRID core at the end of the conceptual design phase - Christophe Venard (CEA)

14:10 Fundamental Approaches to High-power Fast Reactor Core Development - Elena Rodina (Innovative &Technology Center by "PRORYV" Project)

14:30 Specific features of BN-1200 core in case of use of nitride or MOX fuel - Sergey Belov (JSC “Afrikantov OKBM”)
13:30 - 15:10
Room: Room 2
Contributions

13:30 OPERATING EXPERIENCE OF FBTR - SURESH KUMAR K.V (INDIRA GANDHI CENTRE FOR ATOMIC RESEARECH)

13:50 R&D status on in-sodium ultrasonic transducers for ASTRID inspection - Francois Baque (CEA)

14:10 Proposal of Basic Principles of Maintenance Management for Prototype Reactors - Shigeru Takaya (Japan Atomic Energy Agency)

14:30 EXPERIENCE OF COMMISSIONING OF THE SECTORAL MONITORING TIGHTNESS SYSTEM OF FUEL ELEMENTS CLADDINGS (SSKGO) OF RF BN-600, RF BN-800 - Dmitry Lukyanov (JSC «SSC RF-IPPE»)

14:50 Design modifications of Instrumentation & Control System of future FBRs - Venkatesan Arasappan (Indira Gandhi Centre for Atomic Research)
13:30 - 15:10
Room: Room 3
Contributions

13:30 Safety assurance of the new generation of the Russian fast liquid metal reactors - Leonid Bolshov (Nuclear Safety Institute of the Russian Academy of Sciences)

13:50 Development of Safety Design Criteria for the Lead-cooled Fast Reactor - Kamil Tucek (European Commission, Joint Research Centre)

14:10 DETERMINISTIC SAFETY ANALYSIS OF REACTOR BREST-OD-300 - Andrei Stremin (JSC NIKIET, Moscow/Russia)

14:30 SFR INHERENT SAFETY FEATURES AND CRITERIA ANALYSIS - Aleksey Bochkarev (NRC "Kurchatov Institute")

14:50 Evolution of the collective radiation dose from the nuclear reactors through the 2nd to the 4th generation. - anne saturnin (CEA)
13:30 - 15:10
Room: Room 4
Contributions

13:30 A comprehensive study of the dissolution of spent SFR MOX fuel in boiling nitric acid (the PHENIX NESTOR-3 case) - NATHALIE REYNIER TRONCHE (CEA, Nuclear Energy Division, RadioChemistry and Processes Department) emilie buravand (CEA MARCOULE)

13:50 The actinide oxides preparation by thermal denitration - Konstantin Dvoeglazov (Institution Innovation and Technology Center by “PRORYV” Project)

14:30 First assessment of a digestion method applied to recover plutonium from refractory residues after dissolving spent SFR MOX fuel in nitric acid - NATHALIE REYNIER TRONCHE (CEA, Nuclear Energy Division, RadioChemistry and Processes Department) emilie buravand (CEA MARCOULE)

14:50 Pu recycling capabilities of ASTRID reactor - Christophe Venard (CEA)
13:30 - 15:10
Room: Room 5
Contributions

13:30 Development and Demonstration of Ultrasonic Under-Sodium Viewing System for SFRs - Hual-Te Chien (Argonne National Laboratory)

13:50 Stainless Steels Corrosion in Sodium Fast Reactor: Feedback from Risks during Maintenance Operations (SCC in Caustic Solution and Intergranular Corrosion by Acid Solution) - Martine BLAT YRIEIX (EDF R&D MMC)

14:10 Chemical compatibility with liquid sodium after in service solicitations: feedback on stainless steel in French sodium Fast reactor after 35 years of operation - THEODORE COZZIKA (CEA MARCOULE)

14:30 Testing of electrochemical hydrogen meter in a sodium facility in Cadarache - Marianne GIRARD (Commissariat à L'Energie Atomique et aux Energies Alternatives)

14:50 Mass Transfer Simulation Model for Justification Sodium Purification System Characteristics - Eugeny Varseev (ROSATOM-CICE&T)
13:30 - 15:10
Room: Room 6
Contributions

13:30 Codes of New Generation Developed for Breakthrough Project - Valery Strizhov (Nuclear Safety Institute)

13:50 Research and Development on Simulator of Fast Reactor in China - ZhiGang ZHANG (Harbin Engineering University) ZhiJian Zhang (Harbin Engineering University)

14:10 Neutronics Experimental Verification for ADS with China Lead-based Zero Power Reactor - qingsheng wu (Institute of Nuclear Energy Safety Technology, CAS · FDS Team)

14:30 Coupled calculations for the fast reactors safety justification with the EUCLID/V1 integrated computer code - Nastasia Mosunova (Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN))

14:50 Simulating circulating-fuel fast reactors with the coupled TRACE-PARCS code - Eirik Eide Pettersen (Paul Scherrer Institut)
15:10 Coffee Break
Coffee Break
15:10 - 15:30
15:30
15:30 - 17:30
Room: Room 1
Contributions

15:30 Study for Accelerator-driven System in J-PARC/JAEA - Toshinobu Sasa (Japan Atomic Energy Agency)

15:50 The evolution of the primary system design of the MYRRHA facility - Rafael Fernandez (Belgian Nuclear Research Centre (SCK.CEN))

16:10 Physical and technical basics of the concept of a competitive gas cooled fast reactor facility with the core based on coated fuel microparticles - Andrey Balanin (NRC "KurchatovI Institute")

16:30 The ALLEGRO experimental Gas Cooled Fast Reactor Project - János Gadó (MTA EK)

16:50 Design Evolutions of the Molten Salt Fast Reactor - Delphine GERARDIN (FRANCE / LPSC-IN2P3-CNRS - Université Grenoble Alpes)
15:30 - 17:30
Room: Room 3
Contributions

15:30 Current Thermal Hydraulic Activities on Sodium-cooled Fast Reactors in Japan - Akira Yamaguchi (The University of Tokyo)

15:50 Design Safety Limits for Transients in a Metal Fuelled Reactor - CLEMENT RAVI CHANDAR SOWRINATHAN (INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)

16:10 SOCRAT-BN integral code for safety analysis of NPP with sodium cooled fast reactors: development and plant applications - Nikita Rtishchev (IBRAE RAN) Ruslan Chalyy (IBRAE RAN)

16:30 Thermal-hydraulics and Decay Heat Removal in GFR ALLEGRO - Alfredo Vasile (CEA)

16:50 Autonomous Reactivity Control - Staffan Qvist (LeadCold AB)

17:10 Sensitivity studies of SFR unprotected transients with global neutronic feedback coefficients - Paul Gauthé (CEA)
15:30 - 17:30
Room: Room 4
Contributions

15:30 ADVANCED FLOW-SHEET FOR PARTITIONING OF TRIVALENT ACTINIDES FROM FAST REACTOR HIGH ACTIVE WASTE - Balija Sreenivasulu (IGCAR)

15:50 Pyrochemical recycling of the nitride SNF of fast neutron reactors in molten salts as a part of the short-circuited nuclear fuel cycle - Alexei Potapov (Institute of High Temperature Electrochemistry)

16:10 DYNAMIC TEST OF EXTRACTION PROCESS FOR AMERICIUM PARTITIONING FROM THE PUREX RAFFINATE - Liudmila Tkachenko (Khlopin Radium Institute)

16:30 Fuel cycle studies of Generation IV fast reactors with the SITON v2.0 code and the FITXS burn-up scheme - Máté Gergely Halász (Budapest University of Technology and Economics, Institute of Nuclear Techniques)

16:50 Hot test of technique separation of americium and curium - Andrei Shadrin (Bochvar Institute) Vitaliy Vidanov (INSTITUTION «ITC «PRORYV» PROJECT»)

17:10 External Assessment of the U.S. Sodium-Bonded Spent Fuel Treatment Program - Edwin Lyman (Union of Concerned Scientists)
15:30 - 17:30
Room: Room 5
Contributions

15:30 Methods of controlling concentration of oxygen dissolved in heavy liquid metal coolants (lead and lead-bismuth) of nuclear reactors and test facilities - Aleksandr Legkikh (JSC “SSC RF – IPPE”)

15:50 Materials corrosion in Fast Reactor environment - Concetta Fazio (JRC)

16:10 The Conditioning and Chemistry Programme for MYRRHA - Alexander Aerts (Belgian Nuclear Research Centre)

16:30 Strategies of maintaining appropriate technology of heavy liquid metal coolants in advanced nuclear power plants - Radomir Askhadullin (JSC “SSC RF – IPPE”)

16:50 Development of steam-water cycle chemistry for steam generator of research reactor MBIR - Kirill Shutko (N.A. Dollezhal Research and Development Institute of Power Engineering)

17:10 Helium Recovery from Guard Vessel Atmosphere of the ALLEGRO Reactor - Ladislav Bělovský (ÚJV Řež, a. s.)
15:30 - 17:30
Room: Room 6
Contributions

15:30 Heat transfer and temperature non-uniformities in pin bundles with heavy liquid metal coolant at various spacing ways - Aleksandr Sorokin (SSC RF - IPPE) Julia Kuzina (SSC RF - IPPE)

15:50 Thermal-hydraulic experiments supporting the MYRRHA fuel assembly - Julio Pacio (Karlsruhe Institute of Technology)

16:30 NACIE-UP: a HLM loop facility for natural circulation experiments - Morena Angelucci (University of Pisa)

16:50 Eddy current flowrate and local ultrasonic velocity measurements in liquid sodium - Nico Krauter (Helmholtz-Zentrum Dresden - Rossendorf)
15:30 - 17:30
Room: Room 2
Contributions

15:30 Status and perspectives of industrial supply chain for Fast Reactors - Michele Frignani (Ansaldo Nucleare S.p.A.)

15:50 ASTRID - An original and efficient project organization - Laurent VOLPE (French Atomic Energy Commission)

16:30 FALCON advancements towards the implementation of the ALFRED Project - Michele Frignani (Ansaldo Nucleare S.p.A.)

16:50 The GIF Proliferation Resistance and Physical Protection (PR&PP) Evaluation Methodology: Status, Applications and Outlook - Alexander CHEBESKOV (IPPE)

17:10 Closing Up Nuclear Fuel Cycle In a Two-Component System with Thermal And Fast Neutron Reactors - Oleg Saraev (Russian Federation State Atomic Energy Corporation "Rosatom")
17:30 Coffee Break
Coffee Break
17:30 - 17:50
17:50
17:50 - 19:00
Contributions

17:50 Hydraulic Design and Evaluation of the PHTS Mechanical Pump of PGSFR - HUEE-YOUL YE (Korea Atomic Energy Research Institute)

17:50 Analysis of Irradiation Ability of China Experimental Fast Reactor - Xiaoliang Chen (China Institute of Atomic Energy)

17:50 Analyses of unprotected transients in GFR (ALLEGRO) and SFR reactors supporting the group constant generation methodology - Bálint Batki (Centre for Energy Research, Hungarian Academy of Sciences)

17:50 Potential Capabilities in Transmutation of Minor Actinides of the BOR-60 Reactor and MBIR Reactor under Construction - Igor Zhemkov (JSC “SSC RIAR”)

17:50 Expriment and Analysis of Flow distribution of MOX Assembly - Huanjun Zhu (CEFR)

17:50 Nuclear Reactor Modelling and Simulation Toolkit (NuReMoST) –Numerical Reactor Model Configuration System with Interface to Simulation Codes - Chirayu Batra (IAEA)

17:50 Development and Applications of Nuclear Design and Safety Assessment Program SuperMC for Fast Reactor - liqin hu (Institute of Nuclear Energy Safety Technology, CAS · FDS Team)

17:50 NEW NEUTRONIC CALCULATION CODES BASED ON DISCRETE ORDINATES METHOD USING METHODS OF FINITE DIFFERENCES AND FINITE ELEMENTS - Valery Bereznev (IBRAE)

17:50 Computational Analysis Code Development for Emergency Heat Removal of Pool-style Fast Reactors - Xiuli Xue (Senior engineer)

17:50 Concept of multifunctional fast neutron research reactor (MBIR) core with metal (U-Pu-Zr)-fuel - Victor Blandinskiy (NRC "Kurchatov Institute")

17:50 Development of innovating Na leak detector on pipes - Marianne GIRARD (CEA/FRANCE)

17:50 Inspection specifications leading to extended ASTRID Design rules - Francois Baque (CEA)

17:50 Advanced Coupling Methodology for Thermal-hydraulic calculations - JEAN-MARIE HAMY (AREVA NP)

17:50 DESIGN VALIDATION OF PFBR FUEL SUBASSEMBLY TRANSPORTATION CASK WITH MOCKUP TRIAL RUN - Puthiyavinayagam Pillai (Indira Gandhi Centre for Atomic Research)

17:50 CALCULATION OF NEUTRONIC PARAMETERS IN SUPPORT OF A BOR-60 EXPERIMENTAL FA WITH MODERATING ELEMENTS - Artem Varivtcev (JSC “SSC RIAR”)

17:50 Calculation and Experimental Data Analysis of Neutron Spatial/Energy Distribution in the BOR-60 Blanket - Yury Naboyshchikov (JSC "State Scientific Center - Research Institute of Atomic Reactors")

17:50 Design and Fabrication of Closed Loop Systems (CLS) for the Fast Flux Test Facility (FFTF) - David Wootan (Pacific Northwest National Laboratory)

17:50 ANALYSIS OF VARIOUS APPROXIMATIONS IN NEUTRONIC CALCULATIONS OF TRANSIENT IN FAST REACTORS - Irina Chernova (Nuclear Safety Institute of Russian Academy of Sciences)

17:50 Features of the physics of the MBIR reactor core - Vladimir Eliseev (SSC RF-IPPE)

17:50 Modeling of Phenix End-of-Life control rod withdrawal tests with the Serpent-DYN3D code system - Emil Fridman (Helmholtz-Zentrum Dresden-Rossendorf)

17:50 Development and Validation of EBRDYN code by Benchmark Analysis of EBR-II SHRT-17 Test - Partha Sarathy UPPALA (IGCAR, INDIA)

17:50 Application of CFD simulation to validate the BREST-OD-300 primary circuit design - Alexey Tutukin (Vladimirovich)

17:50 LES-SIMULATION OF HEAT TRANSFER IN A TURBULENT PIPE - Konstantin Sergeenko (Michailovich)

17:50 Evaluation of data and model uncertainties and their effect on the fuel assembly temperature field of the ALFRED Lead-cooled Fast Reactor - Francesco Lodi (University of Bologna)

17:50 Overview of Experiments for Physics of Fast Reactors from the International Handbooks of Evaluated Criticality Safety Benchmark Experiments and Evaluated Reactor Physics Benchmark Experiments - Evgeny Rozhikhin (IPPE)

17:50 Evaluation of the OECD/NEA/SFR-UAM Neutronics Reactivity Feedback and Uncertainty Benchmarks - Nicolas Stauff (Argonne National Laboratory)

17:50 Results of old and program of new experiments on the small-sized fast multiplying systems with HEU / LEU fuel for receiving the benchmark data on criticality - Svyatoslav Sikorin (Nikolaevich)

17:50 Burnup Analysis for BN-600 Reactor Core fueled with MOX fuel and Minor Actinides - Moustafa Aziz Ibrahim (Nuclear and Radiological Regulatory authority)

17:50 Uncertainty Quantification of EBR-II Loss of Heat Sink Simulations with SAS4A/SASSYS-1 and DAKOTA - Thomas Fanning (Argonne National Laboratory)

17:50 Development of Research Nuclear Power Facility with MBIR Multi-Purpose Fast Neutron Research Reactor - Alexander Tuzov (JSC "SSC RIAR")

17:50 Impact of nuclear data uncertainties on the reactivity coefficients of ALFRED - Giacomo Grasso (Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA))

17:50 Benchmark Analysis of EBR-II SHRT45R using MARS-LMR - Chiwoong CHOI (Korea Atomic Energy Research Institute (KAERI))

17:50 Investigation of the homogenization effect in sodium void reactivity in PGSFR - Jong Hyuck Won (KAERI)

17:50 Comparative analysis of nuclear energy lexicon - Nikolay Maksimov (National research nuclear university (Moscow Engineering Physics Institute))

17:50 Preliminary Design of Zero Power Reactor for CEFR MOX Core - Qi Zhou (China Institute of Atomic Energy)

17:50 Experiences during construction & Commissioning of electrical power Generation and Evacuation systems in PFBR - Rajan Babu Vinayagamoorthy (Director (Technical))

17:50 Numerical Analysis of EBR-II Shutdown Heat Removal Test-17 using 1D Plant Dynamic Analysis Code coupled with 3D CFD Code - norihiro doda (Japan Atomic Energy Agency)

17:50 Study about the transient characteristics of the unprotected loss of flow accident in a metal fuel sodium cooled fast reactor based on the SAS4A code - Pengrui Qiao (China Institute of Atomic Energy, Beijing, China)

17:50 Lessons Learned from Fast Flux Test Facility Experience - David Wootan (Pacific Northwest National Laboratory)

17:50 The U.S. Knowledge Preservation Program for Fast Flux Test Facility Data - David Wootan (Pacific Northwest National Laboratory)

17:50 Passive Safety Testing at the Fast Flux Test Facility Relevant to New LMR Designs - David Wootan (Pacific Northwest National Laboratory)

17:50 Features of the time dependence of the intensity of delayed neutrons in the range of 0.02 s in the fission 235U by thermal and fast neutrons. - Konstantin Mitrofanov (JSC “SSC RF – IPPE”)

17:50 The relative yields and half-lives of precursors of delayed neutrons in the fission 241Am by fast neutrons. - Konstantin Mitrofanov (JSC “SSC RF – IPPE”)

17:50 Validation of the evaluated fission product yields data from the fast neutron induced fission of 235U, 238U, 239Pu - Dmitriy Gremyachkin (JSC “SSC RF – IPPE”)

17:50 Actual Status of the Development of Multigroup XS Libraries for the Gas-cooled Fast Reactor in Slovakia - Štefan Čerba (Slovak University of Technology in Bratislava)

17:50 SIMMER ANALYSES OF THE EBR-II SHUTDOWN HEAT REMOVAL TESTS - Barbara Vezzoni (Karlsruhe Institute of Technology, Germany)

17:50 DEPENDENCE OF INTERMEDIATE HEAT EXCHANGER LIFE ON PRIMARY SODIUM HEATING RATE DURING POWER RAISING - Velusamy K (IGCAR)

17:50 Assessment of Creep Damage Evaluation Methods for Grade 91 Steel in the ASME and JSME Nuclear Codes - Tai Asayama (Japan Atomic Energy Agency)

17:50 THE STUDY OF THERMAL-HYDRAULIC PROCESSES IN THE STEAM GENERATOR OF THE BREST-OD-300 REACTOR FACILITY - Alexandr Semchenkov (JSC NIKIET, Moscow/Russia)

17:50 Detection and analysis of fuel cladding damages using gamma ray spectroscopy - Romain Coulon (CEA LIST)

17:50 EXPERIENCE OF COMMISSIONING OF BN-800 CORE DIAGNOSTIC SYSTEM (SDRU) - Vladimir Danilenko (FSUE «Alexandrov Research Institute of Technology»)

17:50 INTEGRATED R&D TO VALIDATE INNOVATIVE EMERGENCY HEAT REMOVAL SYSTEM FOR BN-1200 REACTOR - Vasiliy Pakholkov (JSC “Afrikantov OKBM”)

17:50 V&V STATUS OF CFD CODES APPLIED TO BN REACTORS - Sergey Rogozhkin (JSC “Afrikantov OKBM”)

17:50 Uncertainty Analysis of Kinetic Parameters for Design, Operation and Safety Analysis of SFRs - Ivan A. Kodeli (Institut Jožef Stefan, Jamova 39, 1000 Ljubljana, Slovenia)

17:50 EBR-II SHRT-17 and SHRT-45R Benchmark Analyses - Tyler Sumner (Argonne National Laboratory)

17:50 PERFORMANCE EVALUATION OF TIN OXIDE BASED SENSOR FOR MONIOTORING TRACE LEVELS OF H2 IN ARGON COVER GAS PLENUM OF FBTR - Balija Sreenivasulu (IGCAR)

17:50 Overview of the international cooperation and collaboration activities initiated and performed under the Technical Working Group on Fast Reactors in last 50 years - Stefano Monti (IAEA)

17:50 Participation of Mexico in the OECD/NEA SFR Benchmark using the Monte Carlo code Serpent - Federico Puente Espel (Instituto Nacional de Investigaciones Nucleares)

17:50 LOGOS CFD software application for the analysis of liquid metal coolants in the fuel rod bundles geometries - Dmitry Fomichev (JSC NIKIET)

17:50 System of coordinated calculation benchmarks for a fast reactor with sodium coolant in closed fuel cycle - Georgy Tikhomirov (National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)) Mikhail Ternovykh (National Research Nuclear University MEPhI (Moscow Engineering Physics Institute))

17:50 The approaches to the radiation characteristics of structural elements of the core determination during operation and decommissioning for BN-type reactors - Mikhail Kriachko (Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering named after A. I. Leypunsky")

17:50 More precise definitions of the perturbation theory formulas for reactivity effects calculations - boris abramov (Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering named after A. I. Leypunsky")

17:50 Using of computer code GEFEST800 at the initial stage of NPP operation with BN-800 - Evgeny Seleznev (NUCLEAR SAFETY INSTITUTE OF RUSSIAN ACADEMY OF SCIENCES)

17:50 the simulation of reactor physics for China Experimental Fast Reactor - qiang zhao (Harbin Engineering University)

17:50 CFD investigation of thermal-hydraulic characteristics in a SFR fuel assembly - Jae-Ho Jeong (KAERI)

17:50 Development of Safety, Irradiation, and Reliability Databases based on Past U.S. SFR Testing and Operational Experiences - Tanju Sofu (Argonne National Laboratory)

17:50 Methodical uncertainty of criticality precise calculations for fast lead reactor - Ksenia Kalugina (JOINT-STOCK COMPANY «N.A. DOLLEZHAL RESEARCH AND DEVELOPMENT INSTITUTE OF POWER ENGINEERING») Varvara Yufereva (JSC «N.A. Dollezhal Research and Developmant Institute of Power Engineering»)

17:50 Low-void-effect sodium-cooled core: Uncertainty of local sodium void reactivity as a result of nuclear data uncertainties - Sandro Pelloni (Paul Scherrer Institute)

17:50 Scoping Analysis of STELLA-2 using MARS-LMR - Jewhan Lee (KAERI)

17:50 Thermal design of double helium gas gap conduction test facility - Song LI (engineer)

17:50 Russian Companies’ involvement in CEFR RP (China) construction - Igor Petrov (JSC “Afrikantov OKBM”)

17:50 Development experience for experimental reactor facility cooled vith evaporating liquid metals - Nikolay Loginov (SSC RF-IPPE)

17:50 Characterization of LBE Non-isothermal Natural Circulation by Experiments with HELIOS Test Loop and Numerical Analyses - Yonghoon Shin (Seoul National University)

17:50 Computational Analysis Code Development for core and primary system thermal hydraulic design of SFR - Zhiwei Zhou (Engineer)

17:50 Analysis of the EBR-II SHRT-45R neutronics benchmark with ERANOS-2.0 - Willem Frederik Geert Van Rooijen (Research Institute of Nuclear Engineering, University of Fukui)

17:50 Research on modeling and simulation of the primary coolant system for China Experimental Fast Reactor - Zhigang Zhang (Harbin Engineering University)

17:50 Basic Visualization Experiments on Eutectic Reaction of Boron Carbide and Stainless Steel under Sodium-Cooled Fast Reactor Conditions - Hidemasa Yamano (Japan Atomic Energy Agency)
Thursday, 29 June 2017
08:00
08:00 - 10:00
Room: Room 3
Contributions

08:00 Optimization of Passive Safety Devices FAST and SAFE for Sodium-cooled Fast Reactors - Chihyung Kim (Korea Advanced Institute of Science and Techology)

08:40 Impact of an accidental control rod withdrawal on the ALFRED core: tridimensional neutronic and thermal-hydraulic analyses - Massimo Sarotto (Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA))

09:00 Minimisation of Reactivity Margin for Equilibrium Core of Liquid Metal Cooled Fast Reactors - Yury Khomyakov (Private institution «Innovation and technology center for the «PRORYV» project»)
08:00 - 10:00
Room: Room 5
Contributions

08:00 Fabrication and Evaluation of Advanced Cladding Tube for PGSFR - Sung Ho Kim (KAERI)

08:20 Basic principles for lifetime and structural integrity assessment of BN-600 and BN-800 fast reactors components with regard for material degradation - Boris Margolin (Central Research Institute of Structural Materials "Prometey")

08:40 TEM CHARACTERIZATION OF A SWELLING-RESISTANT AUSTENITIC STEEL IRRADIATED AT HIGH TEMPERATURE (>600°C) IN THE PHENIX FAST REACTOR - arnaud courcelle (CEA Saclay)

09:00 Performance evaluation of ferroboron shielding material after irradiation in FBTR - CLEMENT RAVI CHANDAR SOWRINATHAN (INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)

09:20 PREDICTION OF CREEP-RUPTURE PROPERTIES FOR AUSTENITIC STAINLESS STEELS UNDERGONE NEUTRON IRRADIATION AT DIFFERENT TEMPERATURES - Andrey Buchatsky (CRISM "Prometey")

09:40 Recent suppling of 316L(N) stainless steel products for ASTRID - David LALLEMAND (AREVA NP) Laetitia NICOLAS (AREVA) Thosrten MARLAUD (AREVA NP)
08:00 - 10:00
Room: Room 6
Contributions

08:00 The DRESDYN project: A new facility for thermohydraulic studies with liquid sodium - Gunter Gerbeth (Helmholtz-Zentrum Dresden - Rossendorf)

08:20 CIRCE-ICE EXPERIMENTAL ACTIVITY IN SUPPORT OF LMFR DESIGN - Mariano Tarantino (ENEA)

08:40 PLINIUS-2: a new corium facility and programs to support the safety demonstration of the ASTRID mitigation provisions under Severe Accident Conditions - Frédéric SERRE (Commissariat à L'Energie Atomique et aux Energies Alternatives(CEA))

09:00 Sodium testing of fast reactor components - P. Selvaraj (Indira Gandhi Centre For Atomic Research)

09:20 On the rational design of fuel assemblies for reactor facilities from the standpoint of providing vibration strength - Vladislav Sizarev (JSC N.A. Dollezhal Research and Development Institute of Power Engineering)

09:40 CLEAR-S: A Large Pool-type Components and Thermo-hydraulic Integrated Test Facility for China Lead based reactor - Tao Zhou (Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences)
08:00 - 10:00
Room: Room 4
Contributions

08:00 Fast reactor systems in the German P&T and related studies - Andrei Rineiski (Karlsruhe Institute of Technology (KIT))

08:20 Performance Analysis of Various Thorium Fuel Options for the Sodium Cooled Fast Reactor - Myung Hyun Kim (Kyung Hee University)

08:40 Primary Analysis on The Nuclear Energy Development Scenario base on the U-Pu Multicycling with PWR, FR and CNFC in China - Keyuan ZHOU (China Institute of Atomic Energy)

09:00 Analysis of the SVBR-100 nuclear fuel cycle by means of the advanced nuclear fuel cycle assessment methodology (ATTR) - Vladimir Artisyuk (ROSATOM-CICE&T)

09:20 SVBR Project: status and possible development - Georgy Toshinsky

09:40 Fast Neutron Reactors, Fuel Cycles and Problem of Nuclear Non-Proliferation - Alexander Chebeskov (IPPE)
08:00 - 10:00
Room: Room 1
Contributions

08:00 Introduction to the Workshop - Denis Janin

08:15 The Role of the IAEA in Fast Reactor Development and Knowledge Transfer - Chirayu Batra (IAEA)

08:30 Knowledge Transfer and Management for an active fleet of fast reactors - Evgeny Adamov

09:00 Knowledge Transfer and Management with interrupted development - Christian LATGE (CEA Cadarache 13108 Saint Paul lez Durance)

09:30 Knowledge Transfer and Management during long outage periods - Hideki Kamide (Japan Atomic Enery Agency)
10:00 Coffee Break
Coffee Break
10:00 - 10:20
10:20
10:20 - 12:00
Room: Room 3
Contributions

10:20 A Concept of VVER-SCP reactor with fast neutron spectrum and self-provision by secondary fuel - Aleksei Sedov (NRC "Kurchatov Institute")

10:40 Design of a nitride-fueled lead fast reactor for MA transmutation - Sara Bortot (KTH)

11:00 Innovative TRU Burning Fast Reactor Cycle Using Uranium-free TRU Metal Fuel - Core Design Progress - - Kazuo Arie (Toshiba Corporation)

11:20 SEALER: a small lead-cooled reactor for power production in the Canadian Arctic - Janne Wallenius (LeadCold)
10:20 - 12:00
Room: Room 2
Contributions

10:20 Superphenix dismantling - Status and lessons learned - David Settimo (EDF)

10:40 Dependability of the fission chambers for the neutron flux monitoring system of the French GEN-IV SFR - Philippe Filliatre (CEA, DEN, Cadarache, Reactor Studies Department, 13108 Saint-Paul-lez-Durance, France)

11:00 ARRANGEMENT OF THE BN-600 REACTOR CORE REFUELING AT TRANSITION TO THE INCREASED FUEL BURN-UP - Sergey Belov (Joint Stock Company "Afrikantov Experimental Design Bureau for Mechanical Engineering")

11:20 Industrial Exploitation of Testing Ground for Treatment of Radwaste of Alkaline Coolants under Decommissioning of Fast Research Reactors - Kirill Butov (Rosatom, Russian Federation)
10:20 - 12:00
Room: Room 5
Contributions

10:20 The development of a computer code for predicting fast reactor oxide fuel element thermal and mechanical behavior (FIBER-Oxide) - Fuhai Gao (China Institute of Atomic Energy)

11:00 Challenges During Manufacture of Reactor Components of PFBR - Rajan Babu Vinayagamoorthy (Director (Technical))

11:20 Design of Sleeve Valve mechanism for Primary Sodium Pump of future FBR - Puthiyavinayagam Pillai (Indira Gandhi Centre for Atomic Research)
10:20 - 12:00
Room: Room 6
Contributions

10:20 Development of Flow Identification Technology for the PGSFR Thermal Fluidic Design Validation - Dongjin EUH (Korea Atomic Energy Research Institute)

10:40 Detailed engineering neutron codes for calculations of fast breeder reactors - Alexander Belov (Nuclear Safety Institute the of Russian Academy of Sciences)

11:00 BOR-60 REACTOR OPERATIONAL EXPERIENCE AND EXPERIMENTAL CAPABILITIES - Alexey Izhutov (JSC “SSC RIAR”)

11:20 CALCULATION AND EXPERIMENTAL ANALYSIS OF NEUTRONIC PARAMETERS OF THE BN-800 REACTOR CORE AT THE STAGE OF REACHING FIRST CRITICALITY FOLLOWED BY RATED POWER TESTING - Dmitry Klinov (JSC “SSC RF-IPPE”, Obninsk)

11:40 Justification of arrangement, parameters, and irradiation capabilities of the MBIR reactor core at the initial stage of operation - Andrey Gulevich (SSC RF-IPPE)
10:20 - 12:00
Contributions

10:20 IAEA’s Fast Reactors Knowledge Portals and Catalogues - Chirayu Batra (IAEA)

10:40 IAEA NAPRO Coordinated Research Project: Physical Properties of Sodium Overview of the Reference Database and Preliminary Analysis Results - Stefano Passerini (Argonne National Laboratory)

11:00 Overview of the IAEA Activities in the Field of Fast Reactor Technology Development: Current State and Future Vision - Vladimir Kriventsev (IAEA)

11:20 PERSONNAL TRAINING FOR THE "PRORYV" PROJECT AT THE SEVERSK TECHNOLOGICAL INSTITUTE OF NRNU MEPHI - Mikhail Noskov (STI NRNU MEPhI)
YGE Workshop
YGE Workshop
10:20 - 12:00
Room: Room 1
Contributions

10:20 Knowledge Transfer to Young Generation and Technical Reconstruction of BFS Complex - A Zhukov

10:40 Group Discussion

11:20 Group Presentation

11:50 Workshop Conclusion
12:00 Lunch Break
Lunch Break
12:00 - 13:30
13:30
13:30 - 15:30
Room: Plenary Hall
Contributions

13:30 Introduction to the YGE Panel - Chirayu Batra (IAEA)

13:35 How the Next Generation of People will shape the Next Generation of Nuclear - Luke Lebel (Institut de Radioprotection et de Sûreté Nucléaire)

13:50 Innovative cold trap filtration technologies for reliable and economical exploitation of lead-bismuth eutectic cooled systems - Kristof Gladinez (SCK-CEN)

14:05 Stability and bifurcation analysis of sodium boiling in a GEN IV SFR reactor core - Edouard Bissen (CEA - Cadarache)

14:20 Development of Reverse Flow Blockage Device for Primary Sodium Pumps of Fast Breeder Reactor - ARAVINDAN S (IGCAR)

14:35 Developing an open-source multi-physics tool for simulating advanced nuclear reactors - Eirik Eide Pettersen (Paul Scherrer Institut)

14:50 Development of Tri-iso-Amyl Phospahte (TiAP) based solvent extraction process as an alternate method for the processing of metallic alloy fuels (U-Pu-Zr and UZr) - Balija Sreenivasulu (IGCAR)
15:30 Coffee Break
Coffee Break
15:30 - 15:50
15:50
15:50 - 17:00
Room: Plenary Hall
Contributions

15:50 Concluding Report on the Technical Sessions - Hideki Kamide (Japan Atomic Enery Agency) Leonid Bolshov (Nuclear Safety Institute of the Russian Academy of Sciences)

16:10 Report on Panel 1: Safety Design Guidelines - Vladimir Kriventsev (IAEA)

16:20 Report on Panel 2: Small and Medium sized fast reactors - Stefano Monti (IAEA)

16:30 Report on the Young Generation Event - Christophe Xerri

16:40 Closing Remarks by Conference General Chair - Vyacheslav Pershukov (ROSATOM)

16:50 Closing Remarks by Conference General Co-Chair - Mikhail Chudakov (IAEA)