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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)
Yekaterinburg

        : Sessions
    /     : Talks
        : Breaks
26 Jun 2017
27 Jun 2017
28 Jun 2017
29 Jun 2017
AM
08:30
Opening Session -Mr Vyacheslav Pershukov (ROSATOM) Dr Vladimir Kriventsev (IAEA) (until 09:30) (Plenary Hall)
08:30 Opening Address by Director General, ROSATOM (by video message) - Mr Alexey Likhachev (ROSATOM)   (Plenary Hall)
08:40 Opening Address by Director General, IAEA (by video message) - Mr Yukiya Amano (IAEA)   (Plenary Hall)
08:50 Welcome Note by Conference General Chair - Mr Vyacheslav Pershukov (ROSATOM)   (Plenary Hall)
09:00 Welcome Note by Conference General Co-Chair - Mr Mikhail Chudakov (IAEA)   (Plenary Hall)
09:05 Welcome Note by Deputy Presidential Envoy in the Ural Federation District - Mr Alexander Moiseev   (Plenary Hall)
09:15 Fast Reactor Development and International Cooperation (by Honorary General Chair) - Mr Subhash Chander CHETAL (India)   (Plenary Hall)
09:30 --- Coffee Break ---
10:00
Plenary Session 26 June -Dr Amparo Gonzalez-Espartero (IAEA staff) Mr Mikhail Chudakov (IAEA) (until 11:30) (Plenary Hall)
10:00 Closed fuel cycle technologies based on fast reactors as the corner stone for sustainable development of nuclear power - Mr Evgeny Adamov (Institution “ITC “PRORYV” Project)   (Plenary Hall)
Paper
10:30 Research, development and deployment of fast reactors and related fuel cycle in China - Mr Donghui ZHANG (China)   (Plenary Hall)
11:00 Status of the French Fast Reactor Programme - Mr Sylvestre Pivet (France)   (Plenary Hall)
11:30 --- Lunch Break ---
08:00
Plenary Session 27 June -Dr Vladimir Kriventsev (IAEA) Dr Hideki Kamide (Japan Atomic Enery Agency) (until 10:00) (Plenary Hall)
08:00 Indian Fast Reactor Programme : Status and R&D Achievements - Mr ARUN KUMAR BHADURI (INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)   (Plenary Hall)
Paper
08:30 Current status and future view of the fast reactor cycle technology development in Japan - Mr Yutaka Sagayama (Japan Atomic Energy Agency)   (Plenary Hall)
Material
09:00 Status of Sodium Cooled Fast Reactor Development Program in Korea - Dr JAEWOON YOO (Korea Atomic Energy Research Institute)   (Plenary Hall)
Material
09:30 Research and Pilot Fast Neutron Reactors in Russian Federation as the Ground for Development of Worldwide Commercial Technologies - Mr Alexander Tuzov (JSC "SSC RIAR")   (Plenary Hall)
10:00 --- Coffee Break ---
10:20
1.3 SYSTEM DESIGN AND VALIDATION -Mr RAGHUPATHY S. (Indira Gandhi Centre for Atomic Research, Kalpakkam) Mr Sergey Ruhlin (until 12:00) (Room 1)
10:20 EXPERIMENTAL SEISMIC QUALIFICATION OF DIVERSE SAFETY ROD AND ITS DRIVE MECHANISM OF PROTOTYPE FAST BREEDER REACTOR - Mr RAGHUPATHY S. (Indira Gandhi Centre for Atomic Research, Kalpakkam)   (Room 1)
Material
10:40 Progress in the ASTRID Gas Power Conversion System development - Mr david plancq (CEA)   (Room 1)
Material
11:00 ASTRID FUEL HANDLING ROUTE FOR THE BASIC DESIGN - Mr FRANCK DECHELETTE (CEA)   (Room 1)
Material
11:20 COMPONENT HANDLING SYSTEM : PFBR AND BEYOND - Mr RAGHUPATHY S. (IGCAR, KALPAKKAM)   (Room 1)
Material
11:40 Main operation procedures for ASTRID gas power conversion system - Mr dominique barbier (CEA)   (Room 1)
Paper
10:20
3.3 Probabilistic Safety Assessment -Dr Takashi Takata (Japan Atomic Energy Agency) Mr Pavel Antipin (JSC “Afrikantov OKBM”) (until 12:00) (Room 3)
11:00 Development of Smart Component Based Framework for Dynamic Reliability Analysis of Nuclear Safety Systems - Mr Puthiyavinayagam Pillai (Indira Gandhi Centre for Atomic Research)   (Room 3)
Material
11:20 Dynamic probabilistic risk assessment at a design stage for a sodium fast reactor. - Dr VALENTIN RYCHKOV (EDF R&D)   (Room 3)
Material
11:40 PROBABILISTIC SAFETY ANALYSIS RESULTS FOR BN REACTOR POWER UNITS - Mr Pavel Antipin (JSC “Afrikantov OKBM”)   (Room 3)
Paper
Slides
10:20
5.3 Advanced Fast Reactor Cladding Development I -Dr Liudmila Zabudko (Innovative &Technology Center by "PRORYV" Project) Dr Jeong-Yong Park (Korea Atomic Energy Research Institute) (until 12:00) (Room 5)
10:20 Development of core and structural materials for fast reactors - Dr Tai Asayama (Japan Atomic Energy Agency)   (Room 5)
Material
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 - Dr Vladimir Bobrovskii (M.N. Miheev Institute of Metal Physics of Ural Branch of Russian Academy of Sciences)   (Room 5)
Material
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 - Dr Alexander Sorokin (Central Research Institute of Structural Materials “Prometey”)   (Room 5)
Paper
11:20 IAEA activities in the area of Nuclear Power Reactor Fuel Engineering - Dr Mikhail Veshchunov (IAEA)   (Room 5)
Paper
11:40 Examination of Fast Reactor Materials and Structural Elements at JSC “INM” Premises - Mr Alexander Kozlov (Joint Stock Company "Institute of Nuclear Materials")   (Room 5)
Material
10:20
6.10 Other issues of code development and application -Mrs Nastasia Mosunova (Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN)) Mr Tanju Sofu (Argonne National Laboratory) (until 12:00) (Room 2)
10:20 U.S. Sodium Fast Reactor Codes and Methods: Current Capabilities and Path Forward - Dr Acacia Brunett (Argonne National Laboratory)   (Room 2)
Material
10:40 Validation of Advanced Metallic Fuel Models of SAS4A using TREAT M-Series Overpower Test Simulations - Dr Aydin Karahan (Argonne National Laboratory)   (Room 2)
Paper
11:00 Review of Transient Testing of Fast Reactor Fuels in the Transient REActor Test Facility (TREAT) - Dr Colby Jensen (Idaho National Laboratory)   (Room 2)
Material
11:20 USDOE NEAMS Program and SHARP Multi-Physics ToolKit for High-Fidelity SFR Core Design and Analysis - Mr Tanju Sofu (Argonne National Laboratory)   (Room 2)
Material
10:20
6.3 Neutronics - 1 -Mr Dmitry KLINOV (IPPE) Dr Andrei Rineiski (Karlsruhe Institute of Technology (KIT)) (until 12:00) (Room 6)
10:20 The APOLLO3 scientific tool for SFR neutronic characterization: current achievements and perspectives - Prof. Gerald Rimpault (CEA)   (Room 6)
Paper
10:40 INTEGRAL EXPERIMENTS WITH MINOR ACTINIDES AT THE BFS CRITICAL FACILITIES: STATE-OF-THE-ART SURVEY, REEVALUATION AND APPLICATION - Ms Olga Andrianova (IPPE JSC “SSC RF –IPPE”, 1, Bondarenko sq., Obninsk, Kaluga reg. 249033)   (Room 6)
Material
11:00 International research center based on MBIR reactor – cornerstone for Generation 4 technologies development - Mr Vyacheslav Pershukov (ROSATOM)   (Room 6)
Material
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 - Dr Armando Miguel Gomez Torres (Instituto Nacional de Investigaciones Nucleares)   (Room 6)
Material
11:40 Benchmark Evaluation of Dounreay Prototype Fast Reactor Minor Actinide Depletion Measurements - Dr Tatiana Ivanova (OECD Nuclear Energy Agency)   (Room 6)
Material
10:20
7.2 Economics of Fast Reactors -Dr GILLES MATHONNIERE (CEA) Mr Dmitriy Tolstoukhov (ITCP «PRORYV») (until 12:00) (Room 4)
10:20 Fast Reactors and Nuclear Cogeneration: A Market and Economic Analysis - Mr Michele Frignani (ANN)   (Room 4)
Material
10:40 Providing the competitiveness of nuclear energy in the implementation of PRORYV project - Mr Dmitriy Tolstoukhov (ITCP «PRORYV», Russian Federation)   (Room 4)
Paper
11:00 COMPARATIVE ANALYSIS OF ELECTRICITY GENERATION FUEL COST COMPONENT AT NPPs WITH WWER AND BN-TYPE REACTOR FACILITIES - Dr Viktor Dekusar (Laboratory of Nuclear Fuel Cycle system analysis taking into account National and International tendencies)   (Room 4)
Paper
11:20 How to take into account the fleet composition in order to evaluate Fast Breeder Competitiveness - Mr GILLES MATHONNIERE (CEA)   (Room 4)
Paper
11:40 Equipment cost estimation for pilot demonstration lead-cooled fast-neutron reactor BREST-OD-300 - Mr Nikolay Molokanov (ROSATOM, JSC “NIKIET”, MEPhI)   (Room 4)
Paper
08:00
Plenary Session 28 June -Mr Subhash Chander Chetal Mr Vyacheslav Pershukov (ROSATOM) (until 10:00) (Plenary Hall)
08:00 The European Commission contribution to the development of safe and sustainable fast reactor systems - Jean-Paul Glatz (EC-JRC Karlsruhe)   (Plenary Hall)
08:30 Overview of GEN-IV International Forum Activities. Status and Prospects of Fast Reactors - Mr Francois GAUCHE (GIF)   (Plenary Hall)
09:00 Overview of NEA Activities Related to Fast Reactors - Dr Tatiana Ivanova (OECD Nuclear Energy Agency)   (Plenary Hall)
09:30 INPRO: Fast Reactors and Enhanced Nuclear Energy Sustainability - Mr Jon Phillips (IAEA)   (Plenary Hall)
10:00 --- Coffee Break ---
10:20
Panel 2: Small and Medium sized fast reactors -Dr Stefano Monti (IAEA) (until 12:00) (Plenary Hall)
10:20 Feasibility and Challenges for Self-sustainable Long-Life SMR without Refueling - Prof. Yonghee Kim (Korea Advanced Institute of Science and Technology)   (Plenary Hall)
10:30 SVBR-100 as a possible option for developing countries, why? - Mr Georgy Toshinsky (IPPE)   (Plenary Hall)
Paper
10:40 A safe and competitive lead-cooled small modular fast reactor concept for a short-term deployment - Dr Giacomo Grasso (Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA))   (Plenary Hall)
10:50 Eligibility of Small Molten Salt Fast Reactor (S-MSFR) - Dr Jiri Krepel (Paul Scherrer Institut)   (Plenary Hall)
Material
11:00 Small fast reactors for arctic regions - Dr Staffan Qvist (LeadCold AB)   (Plenary Hall)
08:00
3.7 Core Disruptive Accident Prevention -Prof. Hae-Yong JEONG (Sejong University) Iurii Ashurko (IPPE) (until 10:00) (Room 3)
08:00 Optimization of Passive Safety Devices FAST and SAFE for Sodium-cooled Fast Reactors - Mr Chihyung Kim (Korea Advanced Institute of Science and Techology)   (Room 3)
Material
08:40 Impact of an accidental control rod withdrawal on the ALFRED core: tridimensional neutronic and thermal-hydraulic analyses - Dr Massimo Sarotto (Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA))   (Room 3)
Material
09:00 Minimisation of Reactivity Margin for Equilibrium Core of Liquid Metal Cooled Fast Reactors - Mr Yury Khomyakov (Private institution «Innovation and technology center for the «PRORYV» project»)   (Room 3)
Paper
08:00
5.8 Structural Materials -Dr Sung Ho Kim (Korea Atomic Energy Research Institute (KAERI)) Mr Aleksandr Sorokin (SSC RF-IPPE) (until 10:00) (Room 5)
08:00 Fabrication and Evaluation of Advanced Cladding Tube for PGSFR - Dr Sung Ho Kim (KAERI)   (Room 5)
Material
08:20 Basic principles for lifetime and structural integrity assessment of BN-600 and BN-800 fast reactors components with regard for material degradation - Prof. Boris Margolin (Central Research Institute of Structural Materials "Prometey")   (Room 5)
Material
08:40 TEM CHARACTERIZATION OF A SWELLING-RESISTANT AUSTENITIC STEEL IRRADIATED AT HIGH TEMPERATURE (>600°C) IN THE PHENIX FAST REACTOR - Mr arnaud courcelle (CEA Saclay)   (Room 5)
Material
09:00 Performance evaluation of ferroboron shielding material after irradiation in FBTR - Mr CLEMENT RAVI CHANDAR SOWRINATHAN (INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)   (Room 5)
Paper
09:20 PREDICTION OF CREEP-RUPTURE PROPERTIES FOR AUSTENITIC STAINLESS STEELS UNDERGONE NEUTRON IRRADIATION AT DIFFERENT TEMPERATURES - Dr Andrey Buchatsky (CRISM "Prometey")   (Room 5)
Material
09:40 Recent suppling of 316L(N) stainless steel products for ASTRID - Dr Thosrten MARLAUD (AREVA NP) Mr David LALLEMAND (AREVA NP) Laetitia NICOLAS (AREVA)   (Room 5)
Paper
08:00
6.8 Experimental Facilities -Mr Vladimir Semenov Mr Basant Kumar Nashine (Indira Gandhi Centre for Atomic Research, Kalpakkam) (until 10:00) (Room 6)
08:00 The DRESDYN project: A new facility for thermohydraulic studies with liquid sodium - Dr Gunter Gerbeth (Helmholtz-Zentrum Dresden - Rossendorf)   (Room 6)
Material
08:20 CIRCE-ICE EXPERIMENTAL ACTIVITY IN SUPPORT OF LMFR DESIGN - Dr Mariano Tarantino (ENEA)   (Room 6)
Material
08:40 PLINIUS-2: a new corium facility and programs to support the safety demonstration of the ASTRID mitigation provisions under Severe Accident Conditions - Mr Frédéric SERRE (Commissariat à L'Energie Atomique et aux Energies Alternatives(CEA))   (Room 6)
Material
09:00 Sodium testing of fast reactor components - Mr P. Selvaraj (Indira Gandhi Centre For Atomic Research)   (Room 6)
Paper
09:20 On the rational design of fuel assemblies for reactor facilities from the standpoint of providing vibration strength - Mr Vladislav Sizarev (JSC N.A. Dollezhal Research and Development Institute of Power Engineering)   (Room 6)
Material
09:40 CLEAR-S: A Large Pool-type Components and Thermo-hydraulic Integrated Test Facility for China Lead based reactor - Prof. Tao Zhou (Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences)   (Room 6)
Material
08:00
7.4 Fuel Cycle Analysis -Mrs Anzhelika Khaperskaya (State Corporation ROSATOM, Russian Federation) Mr Huo Xingkai (CIAE) (until 10:00) (Room 4)
08:00 Fast reactor systems in the German P&T and related studies - Dr Andrei Rineiski (Karlsruhe Institute of Technology (KIT))   (Room 4)
Material
08:20 Performance Analysis of Various Thorium Fuel Options for the Sodium Cooled Fast Reactor - Prof. Myung Hyun Kim (Kyung Hee University)   (Room 4)
Material
08:40 Primary Analysis on The Nuclear Energy Development Scenario base on the U-Pu Multicycling with PWR, FR and CNFC in China - Mr Keyuan ZHOU (China Institute of Atomic Energy)   (Room 4)
Material
09:00 Analysis of the SVBR-100 nuclear fuel cycle by means of the advanced nuclear fuel cycle assessment methodology (ATTR) - Mr Vladimir Artisyuk (ROSATOM-CICE&T)   (Room 4)
Material
09:20 SVBR Project: status and possible development - Georgy Toshinsky   (Room 4)
Paper
09:40 Fast Neutron Reactors, Fuel Cycles and Problem of Nuclear Non-Proliferation - Dr Alexander Chebeskov (IPPE)   (Room 4)
Material
08:00
YGE Workshop -Mr Evgeny Adamov Mr Chirayu Batra (IAEA) (until 10:00) (Room 1)
08:00 Introduction to the Workshop - Mr Denis Janin   (Room 1)
08:15 The Role of the IAEA in Fast Reactor Development and Knowledge Transfer - Mr Chirayu Batra (IAEA)   (Room 1)
08:30 Knowledge Transfer and Management for an active fleet of fast reactors - Mr Evgeny Adamov   (Room 1)
09:00 Knowledge Transfer and Management with interrupted development - Dr Christian LATGE (CEA Cadarache 13108 Saint Paul lez Durance)   (Room 1)
09:30 Knowledge Transfer and Management during long outage periods - Dr Hideki Kamide (Japan Atomic Enery Agency)   (Room 1)
10:00 --- Coffee Break ---
10:20
1.8 INNOVATIVE REACTOR DESIGNS -Mr Igor Tretyakov Dr Stefano Monti (IAEA) (until 12:00) (Room 3)
10:20 A Concept of VVER-SCP reactor with fast neutron spectrum and self-provision by secondary fuel - Mr Aleksei Sedov (NRC "Kurchatov Institute")   (Room 3)
Material
10:40 Design of a nitride-­fueled lead fast reactor for MA transmutation - Ms Sara Bortot (KTH)   (Room 3)
Material
11:00 Innovative TRU Burning Fast Reactor Cycle Using Uranium-free TRU Metal Fuel - Core Design Progress - - Mr Kazuo Arie (Toshiba Corporation)   (Room 3)
Material
11:20 SEALER: a small lead-cooled reactor for power production in the Canadian Arctic - Prof. Janne Wallenius (LeadCold)   (Room 3)
Material
10:20
2.3 Decommissioning of Fast Reactors and Radioactive Waste Management -Mr Valery Bezzubtsev (Concern "Rosenergoatom", Russia) Hiroyuki Ohshima (Japan Atomic Energy Agency) (until 12:00) (Room 2)
10:20 Superphenix dismantling - Status and lessons learned - Mr David Settimo (EDF)   (Room 2)
Paper
10:40 Dependability of the fission chambers for the neutron flux monitoring system of the French GEN-IV SFR - Dr Philippe Filliatre (CEA, DEN, Cadarache, Reactor Studies Department, 13108 Saint-Paul-lez-Durance, France)   (Room 2)
Paper
11:00 ARRANGEMENT OF THE BN-600 REACTOR CORE REFUELING AT TRANSITION TO THE INCREASED FUEL BURN-UP - Mr Sergey Belov (Joint Stock Company "Afrikantov Experimental Design Bureau for Mechanical Engineering")   (Room 2)
Paper
Slides
11:20 Industrial Exploitation of Testing Ground for Treatment of Radwaste of Alkaline Coolants under Decommissioning of Fast Research Reactors - Mr Kirill Butov (Rosatom, Russian Federation)   (Room 2)
Paper
10:20
5.9 Large Component Technology II -Dr Hyungmo Kim (KAERI) Julia Kuzina (SSC RF - IPPE) (until 12:00) (Room 5)
10:20 The development of a computer code for predicting fast reactor oxide fuel element thermal and mechanical behavior (FIBER-Oxide) - Mr Fuhai Gao (China Institute of Atomic Energy)   (Room 5)
Material
11:00 Challenges During Manufacture of Reactor Components of PFBR - Mr Rajan Babu Vinayagamoorthy (Director (Technical))   (Room 5)
Material
11:20 Design of Sleeve Valve mechanism for Primary Sodium Pump of future FBR - Mr Puthiyavinayagam Pillai (Indira Gandhi Centre for Atomic Research)   (Room 5)
Paper
10:20
6.9 Research Reactors -Dr Hidemasa Yamano (Japan Atomic Energy Agency) Mr Alexander Tuzov (Joint Stock Company "State Scientific Center - Research Institute of Atomic Reactors") (until 12:00) (Room 6)
10:20 Development of Flow Identification Technology for the PGSFR Thermal Fluidic Design Validation - Dr Dongjin EUH (Korea Atomic Energy Research Institute)   (Room 6)
Paper
10:40 Detailed engineering neutron codes for calculations of fast breeder reactors - Mr Alexander Belov (Nuclear Safety Institute the of Russian Academy of Sciences)   (Room 6)
Material
11:00 BOR-60 REACTOR OPERATIONAL EXPERIENCE AND EXPERIMENTAL CAPABILITIES - Mr Alexey Izhutov (JSC “SSC RIAR”)   (Room 6)
Material
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 - Mr Dmitry Klinov (JSC “SSC RF-IPPE”, Obninsk)   (Room 6)
Paper
11:40 Justification of arrangement, parameters, and irradiation capabilities of the MBIR reactor core at the initial stage of operation - Mr Andrey Gulevich (SSC RF-IPPE)   (Room 6)
Paper
10:20
8.2 Professional Development and Knowledge Management - II -Dr Concetta Fazio (JRC) Mr Georgy Tikhomirov (NRNU MEPHI) (until 12:00) ()
10:20 IAEA’s Fast Reactors Knowledge Portals and Catalogues - Mr Chirayu Batra (IAEA)   ()
Paper
10:40 IAEA NAPRO Coordinated Research Project: Physical Properties of Sodium Overview of the Reference Database and Preliminary Analysis Results - Dr Stefano Passerini (Argonne National Laboratory)   ()
Material
11:00 Overview of the IAEA Activities in the Field of Fast Reactor Technology Development: Current State and Future Vision - Dr Vladimir Kriventsev (IAEA)   ()
Material
11:20 PERSONNAL TRAINING FOR THE "PRORYV" PROJECT AT THE SEVERSK TECHNOLOGICAL INSTITUTE OF NRNU MEPHI - Mr Mikhail Noskov (STI NRNU MEPhI)   ()
Paper
10:20
YGE Workshop -Mr Chirayu Batra (IAEA) Mr Evgeny Adamov (until 12:00) (Room 1)
10:20 Knowledge Transfer to Young Generation and Technical Reconstruction of BFS Complex - Mr A Zhukov   (Room 1)
10:40 Group Discussion   (Room 1)
11:20 Group Presentation   (Room 1)
11:50 Workshop Conclusion   (Room 1)
PM
13:00
1.1 SFR DESIGN & DEVELOPMENT - 1 -Mr joel guidez (CEA) Mr Aleksandr Staroverov (JSC “Afrikantov OKBM”) (until 15:00) (Room 1)
13:00 Advanced Design Features of MOX Fuelled Future Indian SFRs - Mr Puthiyavinayagam Pillai (Indira Gandhi Centre for Atomic Research)   (Room 1)
Material
13:20 Overview of U.S. Fast Reactor Technology R&D Program - Ms Heather Bell (U.S. Department of Energy)   (Room 1)
13:40 Development of the new generation power unit with the BN-1200 reactor - Mr Sergey Shepelev (JSC “Afrikantov OKBM”)   (Room 1)
Material
Slides
14:00 Advanced sodium-cooled fast reactor development regarding GIF safety design criteria - Mr Hiroki Hayafune (JAEA)   (Room 1)
Material
14:20 Current status of GIF collaborations on sodium-cooled fast reactor system - Mr Hiroki Hayafune (JAEA)   (Room 1)
Material
14:40 Feasibility of Burning Wave Fast Reactor Concept with Rotational Fuel Shuffling - Prof. Toru Obara (Tokyo Institute of Technology)   (Room 1)
Paper
13:00
2.1 Commissioning and Operating Experience of Fast Reactors I -Mr Alexander FILIN Mr Suresh Kumar Kannankara Vasudevan (IGCAR, Dept. of Atomic Energy, India) (until 15:00) (Room 2)
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 - Mr Yuriy Nosov (Beloyarsk NPP)   (Room 2)
Paper
13:20 Main R&D objectives and results for under-sodium inspection carriers – Example of the ASTRID matting exceptional inspection carrier. - Mr Francois Baque (CEA)   (Room 2)
Material
13:40 Development of under sodium viewer for next generation sodium-cooled fast reactor - Mr Kosuke Aizawa (Japan Atomic Energy Agency)   (Room 2)
Material
14:00 Manufacture, Installation and Adjustment of the BN-800 Reactor Plant Equipment - Mr Igor Petrov (JSC “Afrikantov OKBM”)   (Room 2)
Paper
14:20 Testing and Qualification of Trailing Cable system for Prototype Fast Breeder Reactor - Mr RAGHUPATHY S. (Indira Gandhi Centre for Atomic Research, Kalpakkam)   (Room 2)
Material
14:40 Safety Upgradation of Fast Breeder Test Reactor - Mr Suresh Kumar K V (Department of Atomic Energy, India, Indira Gandhi Centre for Atomic Reaserch, Kalpakkam, Reactor facilities Group)   (Room 2)
Material
13:00
3.1 Safety Program -Dr Andrei Rineiski (Karlsruhe Institute of Technology (KIT)) Mr Pavel Alekseev (NRC “Kurchatov Institute”) (until 15:00) (Room 3)
13:00 The Status of Safety Research in the Field of Sodium-cooled Fast Reactors in Japan - Prof. Koji Morita (Kyushu University)   (Room 3)
Material
13:20 RECENT ACTIVITIES OF THE SAFETY AND OPERATION PROJECT OF THE SODIUM-COOLED FAST REACTOR IN THE GENERATION IV INTERNATIONAL FORUM - Dr Alfredo Vasile (CEA)   (Room 3)
Paper
13:40 “ASTRID safety design: Radiological confinement improvements compared to previous SFRs” - Mr Stéphane BEILS (AREVA NP)   (Room 3)
Paper
14:00 Safety Assurance for BN-1200 Power Unit During Accidents - Mr Artem Anfimov (Joint Stock Company "Afrikantov Experimental Design Bureau for Mechanical Engineering")   (Room 3)
Paper
Slides
14:20 The SAIGA experimental program to support the ASTRID Core Assessment in Severe Accident Conditions - Mr Frédéric Payot (CEA : Commissariat à l’Energie Atomique et aux Energies Alternatives)   (Room 3)
Material
14:40 Study on Safety Design Concept for future Sodium-cooled Fast Reactors in Japan - Mr Shigenobu Kubo (Japan Atomic Energy Agency)   (Room 3)
Paper
13:00
5.1 Advanced Fast Reactor Fuel Development I -Mr CLEMENT RAVI CHANDAR SOWRINATHAN (INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH) Mr Vladimir Troyanov (JSC "Rosenergoatom Concern") (until 15:00) (Room 5)
13:00 Fabrication Characteristics of Injection-cast Metallic Fuels - Dr Jeong-Yong Park (Korea Atomic Energy Research Institute)   (Room 5)
Paper
13:20 Metal fuel for fast reactors, a new concept - Dr Boris Tarasov (NRNU MEPHI)   (Room 5)
Material
13:40 Development of innovative fast reactor nitride fuel in Russian Federation: state-of-art. - Dr Liudmila Zabudko (Innovative &Technology Center by "PRORYV" Project)   (Room 5)
Paper
14:00 Conceptual design of fuel and radial shielding sub-assemblies for ASTRID - Dr Victor BLANC (CEA)   (Room 5)
Paper
14:20 Development of Electromagnetic Devices for Sodium Cooled Fast Reactor Application - Dr B.K. Nashine (Indira Gandhi Centre for Atomic Research, Kalpakkam (T.N.) - India)   (Room 5)
Material
14:40 Fuel Cladding Chemical Interaction Tests of Irradiated Metallic Fuel - Dr Ju-Seong Kim (Korea atomic energy research institute)   (Room 5)
Material
13:00
6.1 CFD and 3D Modeling -Dr Velusamy Karuppanna Gounder (Indira Gandhi Centre for Atomic Research) Prof. Leonid Bolshov (Nuclear Safety Institute of the Russian Academy of Sciences) (until 15:00) (Room 6)
13:00 Numerical simulation of hydraulics and heat transfer in the BREST-OD-300 LFR fuel assembly - Dr Dmitry Fomichev (JSC NIKIET)   (Room 6)
Material
13:20 Steady State Modelling and Validation of Once Through Steam Generator - Dr Velusamy Karuppanna Gounder (Indira Gandhi Centre for Atomic Research)   (Room 6)
Paper
13:40 Applications of the DNS CONV-3D Сode for Simulations of Liquid Metal Flows - Mrs Vladimir Chudanov (Nuclear Safety Insitute RAS (IBRAE))   (Room 6)
Material
14:00 3D Modeling of Fuel Handling System for PFBR Operator Training Simulator - Mr Venkatesan Arasappan (Indira Gandhi Centre for Atomic Research)   (Room 6)
Material
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)   (Room 6)
Paper
14:40 Modelling and Simulation of Heat Transport System and Steam Power Transition System of CEFR - Prof. Zhao-Fei TIAN (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University)   (Room 6)
Material
13:00
7.1 Sustainability of Fast Reactors -Mr Andrey Gulevich (SSC RF-IPPE) Mr Seiichiro Maeda (Japan Atomic Energy Agency) (until 15:00) (Room 4)
13:00 Current Status of Next Generation Fast Reactor Core & Fuel Design and Related R&D in Japan - Mr Seiichiro Maeda (Japan Atomic Energy Agency)   (Room 4)
Material
13:20 Assessment of a nuclear energy system based on the integral indicator of sustainable development - Mr Vladimir Usanov (JSC «SSC RF-IPPE», State Corporation “ROSATOM”)   (Room 4)
Paper
13:40 Performance and sustainability assessment of nuclear energy deployment scenarios with fast reactors: advanced tools and application - Mr Andrei Andrianov (National Research Nuclear University, MEPhI)   (Room 4)
Material
14:00 Comparison of Innovative Nuclear Energy Systems Based on Selected Key Indicators and Their Weighing Factors - Mr Alexander Yegorov (researcher of Laboratory of Nuclear Fuel Cycle system analysis taking into account National and International tendencies)   (Room 4)
Material
14:40 Evaluation results of BN-1200 compliance with the requirements of GENERATION IV and INPRO - Ms Elena Marova (JSC “Afrikantov OKBM”)   (Room 4)
Paper
Slides
15:00 --- Coffee Break ---
15:10
1.2 SFR DESIGN & DEVELOPMENT - 2 -Mr Sergey Shepelev (JSC «Afrikantov OKBM») Mr Puthiyavinayagam Pillai (Indira Gandhi Centre for Atomic Research) (until 17:10) (Room 1)
15:10 Progress of Design and related Researches of Sodium-cooled Fast Reactor in Japan - Dr Hideki Kamide (Japan Atomic Enery Agency)   (Room 1)
Paper
15:50 Lessons and strategies from PFBR to Future Fast Breeder Reactors - Mr Rajan Babu Vinayagamoorthy (Director (Technical))   (Room 1)
Paper
16:10 Status of ASTRID Nuclear Island Design and Future Trends - Mr JEAN-MARIE HAMY (AREVA NP)   (Room 1)
Material
16:30 Analysis of the Characteristics of the Fast Breeder Reactor with Metallic Fuel - Mr IURII DROBYSHEV (VNIIAES JSC)   (Room 1)
Material
16:50 FASTER Test Reactor Preconceptual Design - Mr Christopher Grandy (Argonne National Laboratory)   (Room 1)
Paper
15:10
3.2 Core Disruptive Accident -Mr Andrey VOLKOV Prof. Koji Morita (Kyushu University) (until 17:10) (Room 3)
15:10 Status of severe accident studies at the end of the conceptual design: feedback on mitigation features - Frédéric BERTRAND (CEA Cadarache)   (Room 3)
Paper
15:30 Source Term Estimation for Radioactivity Release under Severe Accident Scenarios in Sodium cooled Fast Reactors - Dr Vladimir Kriventsev (IAEA)   (Room 3)
Material
15:50 Advances in the Development of the SAS4A Code Metallic Fuel Models for the Analysis of PGSFR Postulated Severe Accidents - Mr Seok-Hun Kang (KAERI)   (Room 3)
Paper
16:10 Computational modeling of flow blockage in fuel subassemblies and molten material relocation in sodium cooled fast reactors - Dr Velusamy Karuppanna Gounder (IGCAR)   (Room 3)
Material
16:30 Quantitative Evaluation of the Post Disassembly Energetics of a Hypothetical Core Disruptive Accident in a Sodium Cooled Fast Reactor - Dr Barbara Vezzoni (Karlsruhe Institute of Technology (KIT)) Mr MIchael Flad (Karlsruhe Institute of Technology)   (Room 3)
Material
16:50 An assessment of transient over-power accident in the PGSFR - Dr KWI LIM LEE (KAERI)   (Room 3)
Paper
15:10
4.1 Fuel Cycle Overview -Dr Vitaliy Vidanov (INSTITUTION «ITC «PRORYV» PROJECT») Prof. Christophe POINSSOT (French Nuclear and Alternative Energy Commission) (until 17:10) (Room 4)
15:10 1992-2017: 25 years of success story for the Development of Minor Actinides Partitioning Processes - Prof. Christophe POINSSOT (French Nuclear and Alternative Energy Commission)   (Room 4)
Material
15:30 Comparison of fast reactors performance in the closed U-Pu and Th-U cycle - Dr Jiri Krepel (Paul Scherrer Institut)   (Room 4)
Paper
15:50 Reprocessing of fast reactors mixed U-Pu used nuclear fuel: studies and industrial test - Andrei Shadrin (Bochvar Institute)   (Room 4)
Material
16:10 Overview of the Nuclear Energy Agency Scientific Activities on Advanced Fuel Cycles - Dr Stéphanie Cornet (Nuclear Energy Agency)   (Room 4)
Material
16:30 Assessment of the anticipated improvement of the environmental footprint of future nuclear energy systems - Prof. Christophe POINSSOT (French Nuclear and Alternative Energy Commission)   (Room 4)
Material
16:50 Concurrent Trends in Indian Fast Reactor Fuel Reprocessing Programme - Mr KODANDARAMAN J (INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)   (Room 4)
Material
15:10
5.2 Advanced Fast Reactor Fuel Development II -Dr Victor BLANC (French Atomic Energy Commission) Dr Mikhail Veshchunov (IAEA) (until 17:10) (Room 5)
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) - Mr E. Vázquez (National Atomic Energy Commission of Argentina (CNEA)) Mr Osvaldo Azpitarte (National Atomic Energy Commission of Argentina (CNEA))   (Room 5)
Material
15:30 Effects of Oxygen Partial Pressure During Sintering at Laboratory and Industrial Scales on FR MOX Fuels - Mr Stephane Vaudez (CEA)   (Room 5)
Material
15:50 Fuel Melting Margin Assessment of Fast Reactor Oxide Fuel Pins using a Statistical Approach - Dr Victor BLANC (CEA)   (Room 5)
Paper
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 - Dr Kamil Tucek (European Commission, Joint Research Centre)   (Room 5)
Material
16:30 Fission product and swelling behaviour in FBTR mixed carbide fuel - Mr Suresh Kumar Kannankara Vasudevan (IGCAR, Dept. of Atomic Energy, India)   (Room 5)
Material
16:50 Analysis of experimental data on fission gas release and swelling in mononitride fuel irradiated in BR-10 reactor - Mr Sergey Porollo (IPPE)   (Room 5)
Material
15:10
6.11 IAEA Benchmark on EBR-II Shutdown Heat Removal Tests -Dr Ethan Bates (TerraPower LLC.) Dr Vladimir Kriventsev (IAEA) (until 17:10) (Room 2)
15:15 IAEA’s Coordinated Research Project on EBR-II Shutdown Heat Removal Tests: An Overview - Dr Vladimir Kriventsev (IAEA)   (Room 2)
Material
15:25 EBR-II Passive Safety Demonstration Tests Benchmark Analyses - Ms Laural Briggs (Argonne National Laboratory)   (Room 2)
Material
15:45 IAEA NEUTRONICS BENCHMARK FOR EBR-II SHRT-45R - Mr Wilfred Van Rooijen (Research Institute of Nuclear Engineering (RINE), University of Fukui, (Japan)) Ms Barbara Vezzoni (Karlsruhe Institute of Technology (Germany))   (Room 2)
Material
16:05 Conclusions of a Benchmark Study on the EBR-II SHRT-45R Experiment - Ms Dalin Zhang (Xi'an Jiaotong University) Dr Ethan Bates (TerraPower)   (Room 2)
Material
16:25 Thermal Hydraulic Investigation of EBR-II Instrumented Subassemblies during SHRT-17 and SHRT-45R Tests - Mr Partha Sarathy UPPALA (Indira Gandhi Centre for Atomic Research)   (Room 2)
Material
16:45 Final Results and Lessons Learned from EBR-II SHRT-17 Benchmark Simulations - Mr Nikita Rtishchev (IBRAE RAN)   (Room 2)
Material
15:10
6.2 Thermal Hydraulics Calculations and Experiments -Mrs Nastasia Mosunova (Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN)) Mr Selvaraj Perumal (Indira Gandhi Centre For Atomic Research, Department of Atomic Energy, Kalpakkam, India) (until 17:10) (Room 6)
15:10 Thermal Hydraulic Study of Steam Generator of PGSFR - Dr Jonggan Hong (KAERI)   (Room 6)
Material
15:30 EFFECT OF INLET TEMPERATURE AND OPERATING LINEAR HEAT RATING (LHR) ON THE MAXIMUM ACHIEVABLE BURNUP OF MK-1 CARBIDE FUEL IN FBTR - Mr CLEMENT RAVI CHANDAR SOWRINATHAN (IGCAR, INDIA)   (Room 6)
Paper
15:50 Extension to Heavy Liquid Metal coolants of the validation database of the ANTEO+ sub-channel code - Mr Francesco Lodi (University of Bologna)   (Room 6)
Material
16:10 Density of sodium along the Liquid-Vapor Coexistence Curve, including the Critical Point - Dr M. Laura Japas (CNEA - Argentina)   (Room 6)
Paper
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 - Mr Aleksandr Trufanov (SSC RF-IPPE)   (Room 6)
Paper
16:50 Development and Validation of Multi-scale Thermal-Hydraulics Calculation Schemes for SFR Applications at CEA - Mr Yannick Gorsse (CEA-Saclay)   (Room 6)
Paper
17:10 --- Coffee Break ---
17:30
Panel 1: Development and Standardization of Safety Design Criteria (SDC) and Guidelines (SDG) for Sodium Cooled Fast Reactors -Dr Vladimir Kriventsev (IAEA) (until 19:00) ()
17:35 The Safety Design Criteria Development and Summary of Its Update for the Generation-IV SFR Systems (USA/Japan/GIF) - Dr Yasushi OKANO (Japan Atomic Energy Agency)   ()
Material
17:45 The Safety Design Guideline Development for Generation-IV SFR Systems (Japan/GIF) - Mr 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) - Mr Paul Gauthé (CEA)   ()
Material
18:05 Safety criteria for future Indian SFRs (India) - Mr Subhash Chander CHETAL (India)   ()
18:15 Compliance of Korean SFR Safety Design Approaches with Generation-IV Safety Design Criteria (Korea, R. of) - Dr 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   ()
12:00 --- Lunch Break ---
13:30
1.4 CORE AND DESIGN FEATURES - 1 -Mr HIROKI HAYAFUNE (Japan Atomic Energy Agency) Mr Dmitry Klinov (IPPE) (until 15:10) (Room 1)
13:30 SELECTION OF A LAYOUT FOR THE BN-800 REACTOR HYBRID CORE - Mr Artem Kuznetsov (JSC “Afrikantov OKBM”)   (Room 1)
Paper
Slides
13:50 ALLEGRO Core Neutron Physics Studies - Dr Petr Dařílek (VUJE Inc., SK91864 Trnava, Slovak Republic)   (Room 1)
Paper
14:10 BN-800 core with MOX fuel - Mr Artem Kuznetsov (JSC “Afrikantov OKBM”)   (Room 1)
Paper
Slides
14:30 Physics Investigation of a Supercritical CO2–cooled Micro-Modular Reactor (MMR) for Autonomous Load-Follow Operation - Mr Hwan Yeal YU (KAIST)   (Room 1)
Paper
13:30
3.4 Sodium leak/fire and other safety issues -Mr IURII SHVETSOV (Private institution «Innovation and technology center for the «PRORYV» project») Dr Yasushi OKANO (Japan Atomic Energy Agency) (until 15:10) (Room 3)
13:30 Numerical – experimental research in justification of fire (sodium) safety of sodium cooled fast reactors - Mr Olga Myazdrikova (Leypunsky Institute for Physics and Power Engineering (IPPE))   (Room 3)
Material
13:50 Identification of important phenomena under sodium fire accidents based on PIRT process - Dr Mitsuhiro Aoyagi (Japan Atomic Energy Agency)   (Room 3)
Material
14:10 Learning from 1970 and 1980-Era Sodium Fire Experiments - Dr Luke Lebel (Institut de Radioprotection et de Sûreté Nucléaire)   (Room 3)
Material
14:30 SEISMIC SLOSHING EFFECTS IN LEAD-COOLED FAST REACTORS - Mr Marti Jeltsov (KTH Royal Institute of Technology)   (Room 3)
Material
14:50 Evaluation of multiple primary coolant leakages accidents in Monju with consideration of passive safety features - Mr Kazuo YOSHIMURA (Japan Atomic Energy Agency)   (Room 3)
Paper
13:30
5.10 Fuel Modeling and Simulation -Mr Marc LAINET (French Alternative Energies and Atomic Energy Commission (CEA)) Dr Mikhail Veshchunov (IAEA) (until 15:10) (Room 2)
13:30 PROBLEMS OF CALCULATION MODELLING OF NITRIDE FUEL PERFORMANCE: DRAKON CODE - Mr Evgenii Marinenko (Institute for Physics and Power Engineering)   (Room 2)
Material
13:50 3D SIMULATION IN THE PLEIADES SOFTWARE ENVIRONMENT FOR SODIUM FAST REACTOR FUEL PIN BEHAVIOR UNDER IRRADIATION - Dr bruno MICHEL (CEA/DEN/DEC/SESC/LSC)   (Room 2)
Material
14:10 Current status and progression of GERMINAL fuel performance code for SFR oxide fuel pins - Mr Marc LAINET (French Alternative Energies and Atomic Energy Commission (CEA))   (Room 2)
Material
14:30 BERKUT – Best Estimate Code for Modelling of Fast Reactor Fuel Rod Behavior under Normal and Accidental Conditions - Mr Andrey Boldyrev   (Room 2)
Material
14:50 EXPERIENCE AND APPLICABILITY OF HIGH DENSE METAL URANIUM IN ADVANCED BN-REACTORS - Prof. Iulian Golovchenko (Russian Federation)   (Room 2)
Paper
13:30
5.4 Advanced Fast Reactor Cladding Development II -Dr Tai Asayama (Japan Atomic Energy Agency) Mr V. Chuyev (until 15:10) (Room 5)
13:50 Modeling of Processes in Austenitic Steel Produced Under Irradiation in Fast Reactors and Possibilities of Model Practical Application - Mr Alexander Kozlov (Joint Stock Company "Institute of Nuclear Materials")   (Room 5)
Material
14:10 Preliminary Inspection of Spent Fast Reactor Fuel Claddings - Mr Vyacheslav Shikhalev (Joint Stock Company "Institute of Nuclear Materials")   (Room 5)
Material
14:30 OPERABILITY VALIDATION OF FUEL PINS WITH CLADDINGS MADE OF EK164-ID STEEL IN THE BN-600 REACTOR - Mr Sergey Belov (JSC “Afrikantov OKBM”)   (Room 5)
Paper
Slides
14:50 Creep resistance and fracture toughness of recently-developed optimized Grade 92 and its weldments for advanced fast reactors - Dr Lizhen Tan (Oak Ridge National Laboratory)   (Room 5)
Material
13:30
6.4 Neutronics – 2 -Mr Robert Jacqmin (CEA- Cadarache) Mr Evgeny Seleznev (NUCLEAR SAFETY INSTITUTE OF RUSSIAN ACADEMY OF SCIENCES) (until 15:10) (Room 6)
13:30 Stability Analysis of a Liquid Metal Cooled Fast Reactor - Dr Branislav Vrban (B&J NUCLEAR ltd.)   (Room 6)
Material
13:50 Analysis of the BFS-115-1 experiments - Dr Robert Jacqmin (CEA, Cadarache)   (Room 6)
Paper
14:10 Physical start-up test of China Experimental Fast Reactor - Mr Xingkai Huo (China Institute of Atomic Energy)   (Room 6)
Material
14:30 Neutronic evaluation of a GFR of 100 MWt with reprocessed fuel and thorium using SCALE 6.0 and MCNPX - Prof. Claubia Pereira (Universidade Federal de Minas Gerais)   (Room 6)
Material
14:50 Solution of the OECD/NEA SFR Benchmark with the Mexican neutron diffusion code AZNHEX - Prof. EDMUNDO DEL VALLE GALLEGOS (Instituto Nacional de Investigaciones Nucleares (On Sabbatical Leave from IPN-Mexico))   (Room 6)
Paper
13:30
8.1 Professional Development and Knowledge Management - I -Prof. Vladimir Artisiuk (Rosatom Central Institute for Continuing Education&Training (ROSATOM CICE&T)) Dr Tatiana Ivanova (OECD Nuclear Energy Agency) (until 15:10) (Room 4)
13:30 Development and Deployment of Knowledge Management Portal for Fast Breeder Reactors - Mr Venkatesan Arasappan (Indira Gandhi Centre for Atomic Research)   (Room 4)
Material
13:50 Topical issues of training of specialists for fast nuclear power engineering and the closed nuclear fuel cycle - Mr Georgy Tikhomirov (NRNU MEPHI) Mr Vyacheslav Pershukov (ROSATOM)   (Room 4)
Paper
14:10 'EURATOM SUCCESS STORIES’ IN FACILITATING PAN-EUROPEAN E&T COLLABORATIVE EFFORTS - Mr Roger GARBIL (European Commission Euratom Nuclear Fission)   (Room 4)
Material
14:30 GEN IV Education and Training Initiative via Public Webinars - Dr Konstantin Mikityuk (Paul Scherrer Institute)   (Room 4)
Material
14:50 A proposal for a pan-European E&T programme supporting the development and deployment of ALFRED - Ms Sara Bortot (KTH)   (Room 4)
Material
15:10 --- Coffee Break ---
15:30
1.5 LFR DESIGN & DEVELOPMENT -Dr JAEWOON YOO (Korea Atomic Energy Research Institute) Mr Vadim Lemehov (until 17:10) (Room 1)
15:30 Status of Generation-IV Lead Fast Reactor Activities - Dr Alessandro Alemberti (Ansaldo Nucleare SpA)   (Room 1)
Material
15:50 Simplification, the atout of LFR-AS-200 - Dr Luciano Cinotti (Hydromine Nuclear Energy S.a.r.l.)   (Room 1)
Material
16:10 Strategy and R&D status of China Lead-based Reactor - Prof. Qunying Huang (CnINEST)   (Room 1)
Material
16:30 BREST-OD-300 REACTOR FACILITY. DEVELOPMENT STAGES AND JUSTIFICATION - Mr Vadim Lemekhov (JSC NIKIET)   (Room 1)
Paper
15:30
5.5 Large Component Technology I -Mr Boris MARGOLIN Dr Christian LATGE (CEA Cadarache 13108 Saint Paul lez Durance) (until 17:10) (Room 5)
15:30 Experimental qualification of rotatable plug seals for Sodium Fast Reactor on a large scale test stand - Mr karl vulliez (CEA, DEN, SDTC, Laboratoire d’Etanchéité, 30207, Bagnols Sur Cèze France.)   (Room 5)
Paper
15:50 Heat Transfer Performance Test for a Sodium-to-Air Heat Exchanger with an Inclined Finned-Tube Banks - Dr Hyungmo Kim (KAERI)   (Room 5)
Material
16:10 Development of the built-in primary sodium purification system for the - Mr Sergey Rukhlin (JSC “Afrikantov OKBM”)   (Room 5)
Paper
Slides
16:30 ASTRID French SFR: Progress in Sodium Gas Heat Exchanger development - Mr david plancq (CEA)   (Room 5)
Material
15:30
6.5 Uncertainty Analysis and Tools -Prof. Gerald Rimpault (CEA) Mr Arkadii Kiselev (until 17:10) (Room 6)
15:30 Recent and Potential Advances of the HGPT methodology - Prof. Augusto Gandini (Sapienza University of Rome)   (Room 6)
Paper
15:50 Evaluation of βeff measurements from BERENICE programme with TRIPOLI4® and uncertainties quantification - Prof. Gerald Rimpault (CEA)   (Room 6)
Material
16:10 System of Codes and Nuclear Data for Neutronics Calculations of Fast Reactors and Uncertainty Estimation - Dr Gennady Manturov (PhD)   (Room 6)
Paper
Slides
16:30 Sensitivity and Uncertainty Analysis in Best-Estimate modeling for PGSFR Under ULOF Transient - Jaeseok Heo (Korea Atomic Energy Research Institute)   (Room 6)
Paper
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) - Prof. Gerald Rimpault (CEA)   (Room 6)
Paper
17:10 --- Coffee Break ---
17:30
Poster Session 1 (until 19:00) (Poster Area)
17:30 "Peculiarities of behavior of Coated Particle fuel in the core of Fast Gas Reactor BGR-1000" - Mr Aleksei Sedov (NRC "Kurchatov Institute")   (Poster Area)
Material
17:30 (U,Pu)O2-x MOX pellet for Astrid reactor project - Dr Thierry GERVAIS (AREVA)   (Poster Area)
Material
17:30 3-D Core Design of the TRU-Incinerating Thorium RBWR Using Accident Tolerant Cladding - Ms Sandra Bogetic (University of California at Berkeley)   (Poster Area)
Material
17:30 A Conceptual design of engineering-scale plant applied the simplified MA-bearing fuel fabrication process - Mr YOSHIKAZU YAMADA (Japan Atomic Energy Agency)   (Poster Area)
Paper
17:30 A Demand Driven Way of Thinking Nuclear Development – Neutron Physical Feasibility of a Reactor Directly Operating SNF from LWR - Prof. Bruno Merk (University of Liverpool)   (Poster Area)
Paper
17:30 A High Density Uranium Zirconium Carbonitride LEU Fuel for Application in Fast Reactors - Mr S Sikorin (The Joint Institute for Power and Nuclear Research SOSNY of the National Academy of Sciences of Belarus)   (Poster Area)
Material
17:30 A Mechanistic Source Term Calculation for a Metal Fuel Sodium Fast Reactor - Dr David Grabaskas (Argonne National Laboratory)   (Poster Area)
Material
17:30 A Preliminary Study of P&T Scenario on a Sustainable Energy System in China - Mr Yong YANG (China Institute of Atomic Energy)   (Poster Area)
Material
17:30 Advanced Energy Conversion for Sodium-Cooled Fast Reactors - Dr James Sienicki (Argonne National Laboratory)   (Poster Area)
Material
17:30 Advanced Reactor PSA Methodologies for System Reliability Analysis and Source Term Assessment - Dr David Grabaskas (Argonne National Laboratory)   (Poster Area)
Material
17:30 Americium Retention During Metallic Fuel Fabrication - Mr Randall Fielding (Idaho National Laboratory)   (Poster Area)
Material
17:30 An Assessment of Fission Product Scrubbing in Sodium Pools Following a Core Damage Event in a Sodium Cooled Fast Reactor - Dr Matthew Bucknor (Argonne National Laboratory)   (Poster Area)
Material
17:30 APPLICATION OF PHYSICAL MODELING WHEN CALIBRATING HIGH RANGE ELECTROMAGNETIC FLOWMETERS - Mr Vadim Alexandrovich Shurupov (JSC “SSC RF – IPPE”)   (Poster Area)
Paper
17:30 Application of Heterogeneous Fuel Assemblies in the Core of Modular Fast Sodium Reactor - Mr Yaroslav Kotov (National Recearch Centre "Kurchatov Institute")   (Poster Area)
Material
17:30 Assessment of accuracy from the use of point kinetics when analyzing transition processes in high power fast reactor - Dr Igor Suslov (ITC "PRORYV" Project)   (Poster Area)
Material
17:30 Assessment of the reactivity effects of Gas cooled Fast Reactor - Mr Jakub Lüley (Slovak University of Technology)   (Poster Area)
Material
17:30 ASTRID hot cells - Dr Bernard GUILLOU (SEIV)   (Poster Area)
Material
17:30 ASTRID reactor: design overview and main innovative options for Basic Design - Mr FREDERIC CHANTECLAIR (French Alternative Energies and Atomic Energy Commission (CEA))   (Poster Area)
Paper
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 - Mr David Lemasson (EDF)   (Poster Area)
Paper
17:30 BISON for Metallic Fuels Modeling - Christopher Matthews (Los Alamos National Laboratory)   (Poster Area)
Material
17:30 CFD Simulation of Corium / Materials Interaction for Severe Accidents - Mr Stéphane BEILS (AREVA NP)   (Poster Area)
Material
17:30 CHALLENGES DURING CONSTRUCTION OF SODIUM PIPING SYSTEMS FOR 500MWe PROTOTYPE FAST BREEDER REACTOR - Mr Rajan Babu Vinayagamoorthy (Director (Technical))   (Poster Area)
Material
17:30 CHALLENGES IN THE FABRICATION AND RECYCLING OF MIXED CARBIDE FUEL - Mr SUDHIR MISHRA (BHABHA ATOMIC RESEARCH CENTRE, INDIA)   (Poster Area)
Material
17:30 Change in Mechanical Properties of Spent Fast Reactor Claddings - Ms Svetlana Barsanova (Joint Stock Company «Institute of Nuclear Materials»)   (Poster Area)
Material
17:30 Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow - Dr Konstantin Mikityuk (Paul Scherrer Institut)   (Poster Area)
Material
17:30 Code Qualification Plan for an Advanced Austenitic Stainless Steel, Alloy 709, for Sodium Fast Reactor Structural Applications - Mr Krishnamurti Natesan (Argonne National Laboratory)   (Poster Area)
Material
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 - Mr Michael Orlov (Private institution «Innovation and technology center for the «PRORYV» project»)   (Poster Area)
Paper
17:30 Computational investigation of nuclear waste incineration efficiency in a subcritical molten salt driven by 50-100 MeV protons - Dr Zohreh Gholamzadeh (AEOI) Dr Seyed Mohammad Mirvakili (AEOI)   (Poster Area)
Paper
17:30 Computational modelling of inter-wrapper flow and primary system temperature evolution in FBTR under extended Station Blackout - Dr Velusamy Karuppanna Gounder (Indira Gandhi Center for Atomic Research)   (Poster Area)
Material
17:30 Controlling FCCI with Pd in metallic fuel - Dr Michael Benson (Idaho National Laboratory)   (Poster Area)
Material
17:30 Corrosion behavior of tube steel for BREST-OD-300 steam generator - Mr Kirill Shutko (N.A. Dollezhal Research and Development Institute of Power Engineering)   (Poster Area)
Paper
17:30 CORROSION OF 12X18H10T STEEL IN Ce-, Nd- AND U-CONTAINING MOLTEN LiCl-KCl EUTECTIC - Dr Evgeniya Nikitina (Institute of High Temperature Electrochemistry)   (Poster Area)
Material
17:30 DECAY HEAT REMOVAL SYSTEM IN THE SECONDARY CIRCUIT OF THE SODIUM-COOLED FAST REACTOR AND EVALUATION OF ITS CAPACITY - Iurii Ashurko (IPPE)   (Poster Area)
Material
17:30 Decay-heat removal in accidents in fast reactors with liquid metal coolant - Mr IURII SHVETSOV (Private institution «Innovation and technology center for the «PRORYV» project»)   (Poster Area)
Material
17:30 Design and Development of Stroke Limiting Device for Control & Safety Rod Drive Mechanisms (CSRDMs) of future FBRs - Mr RAGHUPATHY S. (Indira Gandhi Centre for Atomic Research, Kalpakkam)   (Poster Area)
Material
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. - Mr Lev Kochetkov (Alexeevich)   (Poster Area)
Paper
17:30 Development of the U.S. Sodium Component Reliability Database - Dr Matthew Denman (Sandia National Laboratories)   (Poster Area)
Material
17:30 Development of Ultra Sub-size Tensile Specimen for Evaluation of Tensile Properties of Irradiated Materials - Mr Puthiyavinayagam Pillai (Indira Gandhi Centre for Atomic Research)   (Poster Area)
Material
17:30 ECOLOGICAL ASPECTS OF THE USE OF FAST REACTORS IN A CLOSED NUCLEAR FUEL CYCLE UNDER THE “PRORYV” PROJECT - Mr RUDOLF ALEXAKHIN (INSTITUTION «ITC «PRORYV» PROJECT»)   (Poster Area)
Material
17:30 ELECTRICAL CONDUCTIVITY OF MOLTEN LiCl-KCl EUTECTIC WITH COMPONENTS OF SPENT NUCLEAR FUEL - Dr Alexander Salyulev (Institute of High Temperature Electrochemistry)   (Poster Area)
Material
17:30 ESFR-SMART: new Horizon-2020 project on SFR safety - Dr Konstantin Mikityuk (Paul Scherrer Institut)   (Poster Area)
Material
17:30 Evaluation of Anticipated Transient without Scram for SM-SFR using SAS4A/SASSYS-1 - Prof. Deokjung Lee (Ulsan National Institute of Science and Technology)   (Poster Area)
Paper
17:30 EVALUATION OF COBALT FREE COATINGS AS HARDFACING MATERIAL CANDIDATES IN SODIUM FAST REACTOR - Dr FABIEN ROUILLARD (CEA)   (Poster Area)
Paper
17:30 Evaluation of irradiation-induced point defects migration during neutron irradiation in modified 316 stainless steel - Mr Yoshihiro Sekio (Japan Atomic Energy Agency)   (Poster Area)
Material
17:30 Examination of ChS-68 Steel Used as a BN-600 Reactor Cladding Material - Mrs Natalia Glushkova (Joint Stock Company «Institute of Nuclear Materials»)   (Poster Area)
Material
17:30 Experience on MOX fuel fabrication for fast reactor at PFPF - Mr Kiichi Suzuki (Japan Atomic Energy Agency)   (Poster Area)
Material
17:30 Extending the grid plate life - Incorporation of lower axial shield for FBTR - Mr Sureshkumar KV (RFG, IGCAR)   (Poster Area)
Material
17:30 Fabrication process of NpO2 pellets - Mr Bangyue YIN (CIAE)   (Poster Area)
Material
17:30 FACILITY FOR ADVANCED FUELS THROUGH THE SOL-GEL METHOD - Mr Balija Sreenivasulu (IGCAR)   (Poster Area)
Material
17:30 Fast Reactors - The Belgian Regulatory Approach - Dr Matthias Vanderhaegen (Federal Agency for Nuclear Control)   (Poster Area)
Material
17:30 Feasibility of MA Transmutation by (MA, Zr)Hx in Radial Blanket Region of Fast Reactor and Plan of Technology Development - Dr Kazumi IKEDA (Mitsubishi FBR Systems, Inc.)   (Poster Area)
Paper
17:30 FEATURES OF THE NUCLEAR FUEL CYCLE SYSTEMS BASED ON JOINT OPERATION OF FAST AND THERMAL REACTORS - Dr Victor Dekusar (Dekusar)   (Poster Area)
Paper
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 - Mr Sergei Terentev (JOIN STOCK COMPANY «SIBERIAN GROUP OF CHEMICAL ENTERPRISES»)   (Poster Area)
Paper
17:30 High temperature design and evaluation of forced draft sodium-to-air heat exchanger in PGSFR - Dr Nak Hyun Kim (Korea Atomic Energy Reasearch Institute)   (Poster Area)
Material
17:30 Impact of the irradiation of an ASTRID-type core during an ULOF with SIMMER-III - Dr Sandra POUMEROULY (EDF R&D)   (Poster Area)
Material
17:30 IMPLEMENTATION STATUS OF CONTAIN-LMR SODIUM CHEMISTRY MODELS INTO MELCOR 2.1 - Dr David Louie (Sandia National Laboratories)   (Poster Area)
Paper
17:30 Improving inherent safety BN-800 by the use of fuel assembly with (U, Pu)C microfuel. - Mr Nikolay Maslov (National Research Centre "Kurchatov Institute" National Research Nuclear University MEPhI (Moscow Engineering Physics Institute))   (Poster Area)
Paper
17:30 INSERTION RELIABILITY STUDIES FOR THE RBC-TYPE CONTROL RODS IN ASTRID - Mr Denis Lorenzo (CEA)   (Poster Area)
Paper
Poster
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")   (Poster Area)
Material
17:30 Investigation of steel corrosion products mass transfer in sodium - Dr Viktor Alekseev (JSC "SSC RF-IPPE")   (Poster Area)
Material
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 - Mr Aleksandr Sorokin (SSC RF-IPPE)   (Poster Area)
Paper
17:30 Isothermal transformation austenite-ferrite in a P92 steel - Dr María Luppo (Argentina Atomic Energy Commission)   (Poster Area)
Material
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 - Mr Vincent Reynaud (CHAMPALLE SAS) Mr Alexander Denisov (Deputy Director International Business Sosny R&D Company)   (Poster Area)
Material
17:30 Main outcomes from the JASMIN project: development of ASTEC-Na for severe accident simulation in Na cooled fast reactors - Mrs NATHALIE GIRAULT (IRSN)   (Poster Area)
Material
17:30 Mathematical modeling of the mononitride nuclear fuel production processes - Mr Igor Peshkichev (RFNC-VNIITF)   (Poster Area)
Paper
17:30 Mechanical and Thermal Properties of (U,Pu)O2-x - Mr Shun Hirooka (Japan Atomic Energy Agency)   (Poster Area)
Paper
17:30 Mechanical Design Evaluation of Fuel Assembly for PGSFR - Dr Kyungho Yoon (Korea Atomic Energy Research Institute)   (Poster Area)
Material
17:30 Model validation of the ASTERIA-FBR code related to core expansion phase based on THINA experimental results - Dr Tomoko Ishizu (Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R))   (Poster Area)
Material
17:30 Modeling of hydrodynamic processes at a large leak of water into sodium in the fast reactor coolant circuit - Ms Olga Myazdrikova (Institute for Physics and Power Engineering named after A.I. Leypunsky” (IPPE))   (Poster Area)
Material
17:30 Modeling of Lanthanide Transport in Metallic Fuels: Recent Progresses - Dr Cetin Unal (LANL)   (Poster Area)
Paper
17:30 Modeling technologies of fuel cycles - Ms Inga Makeyeva (RFNC-VNIITF)   (Poster Area)
Paper
17:30 Multiscale computer modeling of nuclear fuel properties at radiation and thermal impacts - Dr Sergey Starikov (Nuclear Safety Institute of the Russian Academy of Sciences)   (Poster Area)
Paper
17:30 Neutronic Self-sustainability of a Breed-and-Burn Fast Reactor Using Super-Simple Fuel Recycling - Mr Chihyung Kim (Korea Advanced Institute of Science and Techology)   (Poster Area)
Material
17:30 New results on the continuous cooling behavior of an ASTM A335 P92 steel - Dr María Luppo (Argentina Atomic Energy Commission)   (Poster Area)
Material
17:30 Numerical and Experimental Investigations of Tube-to-Tube Interaction of Air Heat Exchangers of PFBR under Seismic Excitations - Dr Velusamy Karuppanna Gounder (Indira Gandhi Centre for Atomic Research)   (Poster Area)
Material
17:30 Numerical Investigation of Sodium Spray Combustion Test with SPHINCS code - Dr Takashi Takata (Japan Atomic Energy Agency)   (Poster Area)
Material
17:30 On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors - Mr Boris Hombourger (Paul Scherrer Institut (PSI), Switzerland; École Polytechnique Fédérale de Lausanne (EPFL), Switzerland)   (Poster Area)
Material
17:30 On the possibility of using various types of fuel in the MBIR reactor core - Mr Pavel Maslov (SSC RF-IPPE)   (Poster Area)
Paper
17:30 On-site nuclear fuel cycle of “BREST” reactors - Mr Andrei Glazov (Institution “Innovation and Technology Center by “PRORYV” Project”, State Atomic Energy Corporation “Rosatom”)   (Poster Area)
Material
17:30 Optimization of the thermomechanical treatment to achieve a homogeneous microstructure in a 14Cr ODS steel - Mr Benjamin Hary (CEA)   (Poster Area)
Paper
17:30 OSCAR-Na validation against sodium loop experiments - Mr Jean-Baptiste GENIN (CEA, DEN)   (Poster Area)
Material
17:30 Overview of the U.S. DOE fast reactor fuel development program - Dr William Carmack (Idaho National Laboratory)   (Poster Area)
Paper
17:30 Passive Complementary Safety Devices for ASTRID severe accident prevention - Mr Edouard Bissen (CEA)   (Poster Area)
Paper
17:30 Passive Shutdown Systems for Liquid Metal-Cooled Fast Reactors - Dr Staffan Qvist (LeadCold AB)   (Poster Area)
Paper
17:30 Possibility studies of a boiling water cooled traveling wave reactor - Dr Xue-Nong Chen (KIT, IKET)   (Poster Area)
Paper
17:30 POSTREACTOR STATE OF THE STANDARD AND EXPERIMENTAL BN-600 FUEL KINDS - Mr Evgenii Kinev (Institute of Nuclear Materials)   (Poster Area)
Material
17:30 Precipitate phases in a weldment of P92 steel - Dr María Luppo (Argentina Atomic Energy Commission)   (Poster Area)
Material
17:30 Preliminary Safety Performance Assessment of ESFR CONF-­2 Sphere-­pac‐Fueled Core - Ms Sara Bortot (KTH)   (Poster Area)
Material
17:30 Preliminary transient analyses of SEALER - Mr Ignas Mickus (LeadCold Reactors)   (Poster Area)
Paper
17:30 Probabilistic Safety Analysis of NPP with BREST-OD-300 reactor - Mr Mikhail Ivochkin (JSC NIKIET, MOSCOW/RUSSIA)   (Poster Area)
Material
17:30 Remote detection of raised radioactivity in emission from Beloyarsk nuclear power plant - Mr Gennady Kolotkov (V.E. Zuev Institute of Atmospheric Optics SB RAS)   (Poster Area)
Material
17:30 Resting Bottom Fast Reactor - Mr Didier Costes (CEA)   (Poster Area)
Poster
17:30 ROUZ CODE: CFD APPROACH FOR ASSESSMENT OF RADIATION SITUATION DURING ATMOSPHERE RADIOACTIVITY RELEASES WITHIN AN INDUSTRIAL SITE - Mr Dmitry Blagodatskykh (Nuclear Safety Institute (IBRAE RAN))   (Poster Area)
Material
17:30 SELECTION OF CARRIER SALT FOR MOLTEN SALT FAST REACTOR - Dr Andrey Lizin (Russian Federation)   (Poster Area)
Paper
17:30 Sensors of content of oxygen dissolved in heavy liquid metal coolants - Mr Roman Sadovnichiy (JSC “SSC RF – IPPE”)   (Poster Area)
Paper
17:30 SIBYLLA CODE: ASSESSMENT OF WATER BODIES CONTAMINATION AND DOSES RECEIVED BY POPULATION DUE TO RADIOACTIVITY DISCHARGES INTO THE HYDROSPHERE - Dr Alexey Krylov (Nuclear Safety Institute of Russian Academy of Sciences)   (Poster Area)
Paper
17:30 Sodium compatibility of Recently-Developed Optimized Grade 92 and its Weldments for Advanced Fast Reactors - Dr Meimei Li (Argonne National Lab)   (Poster Area)
Paper
17:30 STATISTICAL INVESTIGATION OF RADIATION-INDUCED POROSITY IN BN FUEL CLADDINGS USING SCANNING ELECTRON MICROSCOPY - Mr Vladimir Pastukhov (Joint Stock Company "Institute of Nuclear Materials")   (Poster Area)
Material
17:30 Structural Design and Evaluation of a Steam Generator in PGSFR - Mr Chang-Gyu PARK (Korea Atomic Energy Research Institute)   (Poster Area)
Material
17:30 Study of isolation valve for Sodium Fast Reactor - Mr Marc Gosset (AREVA NP) Mr Martin Delmas (VELAN SAS) Mr Gilles Rodriguez (CEA) Mr David Montagnier (AREVA NP) Mr Dominique Villani (AREVA NP) Mr Julien Large (VELAN SAS) Mr Nicolas Crepin (VELAN SAS)   (Poster Area)
Paper
17:30 Study of the austenitization process in a P91 steel - Dr María Luppo (Argentina Atomic Energy Commission)   (Poster Area)
Material
17:30 Study on the limits of confinement leakage rates of pool-type sodium-cooled fast reactor - Mr FENGLONG WANG (CHINA INSTITUTE OF ATOMIC ENERGY,BEIJING,CHINA)   (Poster Area)
Material
17:30 Study on the sensitivity analysis of the installed capacity and the high-level waste generation based on closed nuclear fuel cycle - Dr Yun HU (China Institute of Atomic Energy)   (Poster Area)
Material
17:30 Synergetic mechanism of high temperature radiation embrittlement of austenitic steels under long term neutron irradiation at high temperatures - Dr Victoria Shvetsova (Central Research Institute of Structural Materials “Prometey”)   (Poster Area)
Material
17:30 Testing and Qualification of shielded flasks for handling sodium wetted large sized components of PFBR - Mr Rajan Babu Vinayagamoothy (BHAVINI, Dept of Atomic Energy, Kalpakkam)   (Poster Area)
Paper
17:30 The behavior features of fuel elements with nitride fuel - theory and experiment - Mr Igor Konovalov (National Research Nuclear University "MEPhI")   (Poster Area)
Material
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)   (Poster Area)
Material
17:30 The Commercial Potential of the Dual-Component Nuclear Power System - Mr Mikhail Baryshnikov (Head of Back-End Departement)   (Poster Area)
Paper
17:30 The Computer model for the economic assessment of NPP pilot demonstration energy complex with BREST-OD-300 reactor (REM Proryv Project) - Mr Nikolay Molokanov (ROSATOM, JSC “NIKIET”, MEPhI)   (Poster Area)
Paper
17:30 The concept of 50-300 MWe modular-transportable nuclear power plant with sodium coolant and a gas turbine - Yurij Osheyko (none)   (Poster Area)
Paper
17:30 The core of the LFR-AS-200: robustness for safety - Dr Giacomo Grasso (Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA))   (Poster Area)
Material
17:30 The Effect of Proton Irradiation on the Corrosion Behaviors of Ferritic/Martensitic Steel - Mr Jeonghyeon Lee (UNIST)   (Poster Area)
Paper
17:30 The influence of porosity on thermal conductivity of low-density uranium oxide. - Dr Kyoichi Morimoto (Japan Atomic Energy Agency)   (Poster Area)
Paper
17:30 The lead-cooled fast reactor transition to equilibrium operating conditions - Mr Igor Volkov (Russian Federal Nuclear Center - All-Russia Research Institute of Technical Physics)   (Poster Area)
Paper
17:30 The method of calculating tritium content in various technological media of BN-type reactors - Mr Mikhail Kriachko (Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering named after A. I. Leypunsky")   (Poster Area)
Material
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 - Mr Mikhail Belonogov (RFNC-VNIITF named after academ. E.I. Zababakhin)   (Poster Area)
Material
17:30 The study of U-232 accumulation in reprocessed uranium for fast reactor fuel cycle - Mr Mikhail Kriachko (Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering named after A. I. Leypunsky")   (Poster Area)
Material
17:30 The UO2– MeO2 (Me = Th, Pu, Zr) cathode crystalline deposits formation during the melts electrolysis. - Dr Vladimir Krotov (Institute of High-Temperature Electrochemistry UB RAS)   (Poster Area)
Paper
17:30 The way of nitride fuel producing by high voltage electrodischarge compaction - Ms Maria Tarasova (National research nuclear University "MEPhI")   (Poster Area)
Material
17:30 Thermal and elastic properties of CexTh1-xO2 mixed oxides: a self-consistent thermodynamic approach - Dr Anton Filanovich (Ural Federal University)   (Poster Area)
Paper
17:30 Thermal Annealing Effect on Recovery of Corrosion Properties of EP-450 Steel Irradiated IN BN-600 Reactor to High Damage Doses - Mr Oleg Golosov (Joint Stock Company "Institute of Nuclear Materials")   (Poster Area)
Material
17:30 Thermal conductivity of non-stoichiometric (Pu0.928Am0.072)O2-x - Dr Taku Matsumoto (Japan Atomic Energy Agency)   (Poster Area)
Paper
17:30 Thermal hydraulic investigation of sodium fire and hydrogen production in top shield enclosure of an FBR following a core disruptive accident - Dr Velusamy Karuppanna Gounder (Indira Gandhi Centre for Atomic Research)   (Poster Area)
Material
Slides
17:30 Thermodynamics and separation factor of lanthanides and actinides in system “liquid metal-molten salt” - Prof. Valeri Smolenski (Institute of High-Temperature Electrochemistry UB RAS)   (Poster Area)
Paper
17:30 Towards a new approach for structural materials of Lead Fast Reactors - Dr Pietro Agostini (ENEA)   (Poster Area)
Material
17:30 Tradeoff Study of Advanced Transmutation Fuels in Sodium-cooled Fast Reactors - Dr Nicolas Stauff (Argonne National Laboratory)   (Poster Area)
Material
17:30 TRANSMUTATION TRAJECTORY ANALYSIS IN THE MODELLING OF LFR FUEL CYCLE - Dr Mikołaj Oettingen (AGH University of Science and Technology, Faculty of Energy and Fuels, Department of Nuclear Energy)   (Poster Area)
Material
17:30 Use of ion irradiations to help design of advanced austenitic steels - Dr Yann DE CARLAN (SRMA, CEA Saclay, Université Paris-Saclay, 91191 Gif-sur-Yvette Cedex, France)   (Poster Area)
Material
17:30 VOIDING OF ELSY PRIMARY SYSTEM DURING STEAM GENERATOR LEAKAGE - Mr Marti Jeltsov (KTH Royal Institute of Technology)   (Poster Area)
Material
17:30 X-RAY DIFFRACTION STRUCTURAL ANALYSIS OF STRUCTURAL AND FUEL MATERIALS FOR BN-600 REACTOR - Mr Vladimir Tsygvintsev (Joint Stock Company “Institute of Nuclear Materials”)   (Poster Area)
Paper
12:00 --- Lunch Break ---
13:30
1.6 CORE AND DESIGN FEATURES - 2 -Mr Rajan Babu Vinayagamoorthy (Director (Technical)) Mr Sergey Belov (JSC “Afrikantov OKBM”) (until 15:10) (Room 1)
13:30 CORE CONDITON MONITORING IN ADVANCED COMMERCIAL SODIUM BN-1200 - Mr Ivan Zverev (JSC “Afrikantov OKBM”)   (Room 1)
Paper
Slides
13:50 The ASTRID core at the end of the conceptual design phase - Mr Christophe Venard (CEA)   (Room 1)
Material
14:10 Fundamental Approaches to High-power Fast Reactor Core Development - Mrs Elena Rodina (Innovative &Technology Center by "PRORYV" Project)   (Room 1)
Paper
14:30 Specific features of BN-1200 core in case of use of nitride or MOX fuel - Mr Sergey Belov (JSC “Afrikantov OKBM”)   (Room 1)
Paper
Slides
13:30
2.2 Commissioning and Operating Experience of Fast Reactors II -Mr Andrey Gulevich (SSC RF-IPPE) Mr DAVID SETTIMO (EDF) (until 15:10) (Room 2)
13:30 OPERATING EXPERIENCE OF FBTR - Mr SURESH KUMAR K.V (INDIRA GANDHI CENTRE FOR ATOMIC RESEARECH)   (Room 2)
Paper
13:50 R&D status on in-sodium ultrasonic transducers for ASTRID inspection - Mr Francois Baque (CEA)   (Room 2)
Paper
14:10 Proposal of Basic Principles of Maintenance Management for Prototype Reactors - Dr Shigeru Takaya (Japan Atomic Energy Agency)   (Room 2)
Material
14:30 EXPERIENCE OF COMMISSIONING OF THE SECTORAL MONITORING TIGHTNESS SYSTEM OF FUEL ELEMENTS CLADDINGS (SSKGO) OF RF BN-600, RF BN-800 - Mr Dmitry Lukyanov (JSC «SSC RF-IPPE»)   (Room 2)
14:50 Design modifications of Instrumentation & Control System of future FBRs - Mr Venkatesan Arasappan (Indira Gandhi Centre for Atomic Research)   (Room 2)
Material
13:30
3.5 General Safety Approach -Mr Paul Gauthé (CEA) Prof. Leonid Bolshov (Nuclear Safety Institute of the Russian Academy of Sciences) (until 15:10) (Room 3)
13:30 Safety assurance of the new generation of the Russian fast liquid metal reactors - Prof. Leonid Bolshov (Nuclear Safety Institute of the Russian Academy of Sciences)   (Room 3)
Paper
13:50 Development of Safety Design Criteria for the Lead-cooled Fast Reactor - Dr Kamil Tucek (European Commission, Joint Research Centre)   (Room 3)
Paper
14:10 DETERMINISTIC SAFETY ANALYSIS OF REACTOR BREST-OD-300 - Mr Andrei Stremin (JSC NIKIET, Moscow/Russia)   (Room 3)
Material
14:30 SFR INHERENT SAFETY FEATURES AND CRITERIA ANALYSIS - Mr Aleksey Bochkarev (NRC "Kurchatov Institute")   (Room 3)
Material
14:50 Evolution of the collective radiation dose from the nuclear reactors through the 2nd to the 4th generation. - Mrs anne saturnin (CEA)   (Room 3)
Material
13:30
4.2 Reprocessing and Partitioning -Mr Andrei Glazov (Institution “Innovation and Technology Center by “PRORYV” Project”, State Atomic Energy Corporation “Rosatom”) Dr Stéphanie Cornet (Nuclear Energy Agency) (until 15:10) (Room 4)
13:30 A comprehensive study of the dissolution of spent SFR MOX fuel in boiling nitric acid (the PHENIX NESTOR-3 case) - Ms emilie buravand (CEA MARCOULE) Dr NATHALIE REYNIER TRONCHE (CEA, Nuclear Energy Division, RadioChemistry and Processes Department)   (Room 4)
Paper
13:50 The actinide oxides preparation by thermal denitration - Mr Konstantin Dvoeglazov (Institution Innovation and Technology Center by “PRORYV” Project)   (Room 4)
Material
14:30 First assessment of a digestion method applied to recover plutonium from refractory residues after dissolving spent SFR MOX fuel in nitric acid - Ms emilie buravand (CEA MARCOULE) Dr NATHALIE REYNIER TRONCHE (CEA, Nuclear Energy Division, RadioChemistry and Processes Department)   (Room 4)
Paper
14:50 Pu recycling capabilities of ASTRID reactor - Mr Christophe Venard (CEA)   (Room 4)
Paper
13:30
5.6 Liquid Metal Technologies -Prof. Akira Yamaguchi (The University of Tokyo) Mr Radomir ASKHADULLIN (until 15:10) (Room 5)
13:30 Development and Demonstration of Ultrasonic Under-Sodium Viewing System for SFRs - Dr Hual-Te Chien (Argonne National Laboratory)   (Room 5)
Material
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) - Mrs Martine BLAT YRIEIX (EDF R&D MMC)   (Room 5)
Paper
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 - Mr THEODORE COZZIKA (CEA MARCOULE)   (Room 5)
Paper
14:30 Testing of electrochemical hydrogen meter in a sodium facility in Cadarache - Ms Marianne GIRARD (Commissariat à L'Energie Atomique et aux Energies Alternatives)   (Room 5)
Material
14:50 Mass Transfer Simulation Model for Justification Sodium Purification System Characteristics - Mr Eugeny Varseev (ROSATOM-CICE&T)   (Room 5)
Material
13:30
6.6 Coupled Calculations -Prof. Zhi-gang Zhang (Harbin Engineering University) Prof. Valery Strizhov (Nuclear Safety Institute) (until 15:10) (Room 6)
13:30 Codes of New Generation Developed for Breakthrough Project - Prof. Valery Strizhov (Nuclear Safety Institute)   (Room 6)
Material
13:50 Research and Development on Simulator of Fast Reactor in China - Prof. ZhiJian Zhang (Harbin Engineering University) Prof. ZhiGang ZHANG (Harbin Engineering University)   (Room 6)
Material
14:10 Neutronics Experimental Verification for ADS with China Lead-based Zero Power Reactor - Prof. qingsheng wu (Institute of Nuclear Energy Safety Technology, CAS · FDS Team)   (Room 6)
Material
14:30 Coupled calculations for the fast reactors safety justification with the EUCLID/V1 integrated computer code - Mrs Nastasia Mosunova (Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN))   (Room 6)
Material
14:50 Simulating circulating-fuel fast reactors with the coupled TRACE-PARCS code - Eirik Eide Pettersen (Paul Scherrer Institut)   (Room 6)
Material
15:10 --- Coffee Break ---
15:30
1.7 ADS AND OTHER REACTOR DESIGNS -Dr Stefano Monti (IAEA) Mr Valery Rachkov (Track leader) (until 17:30) (Room 1)
15:30 Study for Accelerator-driven System in J-PARC/JAEA - Dr Toshinobu Sasa (Japan Atomic Energy Agency)   (Room 1)
Paper
15:50 The evolution of the primary system design of the MYRRHA facility - Mr Rafael Fernandez (Belgian Nuclear Research Centre (SCK.CEN))   (Room 1)
Material
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 - Mr Andrey Balanin (NRC "KurchatovI Institute")   (Room 1)
Material
16:30 The ALLEGRO experimental Gas Cooled Fast Reactor Project - Mr János Gadó (MTA EK)   (Room 1)
Material
16:50 Design Evolutions of the Molten Salt Fast Reactor - Ms Delphine GERARDIN (FRANCE / LPSC-IN2P3-CNRS - Université Grenoble Alpes)   (Room 1)
Material
15:30
3.6 Safety Analysis -Dr Staffan Qvist (LeadCold AB) Mr Yury Khomyakov (Private institution «Innovation and technology center for the «PRORYV» project») (until 17:30) (Room 3)
15:30 Current Thermal Hydraulic Activities on Sodium-cooled Fast Reactors in Japan - Prof. Akira Yamaguchi (The University of Tokyo)   (Room 3)
Material
15:50 Design Safety Limits for Transients in a Metal Fuelled Reactor - Mr CLEMENT RAVI CHANDAR SOWRINATHAN (INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)   (Room 3)
Material
16:10 SOCRAT-BN integral code for safety analysis of NPP with sodium cooled fast reactors: development and plant applications - Mr Ruslan Chalyy (IBRAE RAN) Dr Nikita Rtishchev (IBRAE RAN)   (Room 3)
Paper
16:30 Thermal-hydraulics and Decay Heat Removal in GFR ALLEGRO - Dr Alfredo Vasile (CEA)   (Room 3)
Paper
16:50 Autonomous Reactivity Control - Dr Staffan Qvist (LeadCold AB)   (Room 3)
Paper
17:10 Sensitivity studies of SFR unprotected transients with global neutronic feedback coefficients - Mr Paul Gauthé (CEA)   (Room 3)
Material
15:30
4.3 Partitioning and Sustainability - Andrei Shadrin (Bochvar Institute) Dr Amparo Gonzalez-Espartero (IAEA staff) (until 17:30) (Room 4)
15:30 ADVANCED FLOW-SHEET FOR PARTITIONING OF TRIVALENT ACTINIDES FROM FAST REACTOR HIGH ACTIVE WASTE - Mr Balija Sreenivasulu (IGCAR)   (Room 4)
Paper
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 - Prof. Alexei Potapov (Institute of High Temperature Electrochemistry)   (Room 4)
Paper
16:10 DYNAMIC TEST OF EXTRACTION PROCESS FOR AMERICIUM PARTITIONING FROM THE PUREX RAFFINATE - Dr Liudmila Tkachenko (Khlopin Radium Institute)   (Room 4)
Material
16:30 Fuel cycle studies of Generation IV fast reactors with the SITON v2.0 code and the FITXS burn-up scheme - Mr Máté Gergely Halász (Budapest University of Technology and Economics, Institute of Nuclear Techniques)   (Room 4)
Material
16:50 Hot test of technique separation of americium and curium - Dr Vitaliy Vidanov (INSTITUTION «ITC «PRORYV» PROJECT») Andrei Shadrin (Bochvar Institute)   (Room 4)
Paper
17:10 External Assessment of the U.S. Sodium-Bonded Spent Fuel Treatment Program - Dr Edwin Lyman (Union of Concerned Scientists)   (Room 4)
Material
15:30
5.7 Chemistry Related Technology -Mr Aleksandr Legkikh (JSC “SSC RF – IPPE”) Dr Concetta Fazio (JRC) (until 17:30) (Room 5)
15:30 Methods of controlling concentration of oxygen dissolved in heavy liquid metal coolants (lead and lead-bismuth) of nuclear reactors and test facilities - Mr Aleksandr Legkikh (JSC “SSC RF – IPPE”)   (Room 5)
Paper
15:50 Materials corrosion in Fast Reactor environment - Dr Concetta Fazio (JRC)   (Room 5)
Material
16:10 The Conditioning and Chemistry Programme for MYRRHA - Dr Alexander Aerts (Belgian Nuclear Research Centre)   (Room 5)
Material
16:30 Strategies of maintaining appropriate technology of heavy liquid metal coolants in advanced nuclear power plants - Mr Radomir Askhadullin (JSC “SSC RF – IPPE”)   (Room 5)
Paper
16:50 Development of steam-water cycle chemistry for steam generator of research reactor MBIR - Dr Kirill Shutko (N.A. Dollezhal Research and Development Institute of Power Engineering)   (Room 5)
Paper
17:10 Helium Recovery from Guard Vessel Atmosphere of the ALLEGRO Reactor - Dr Ladislav Bělovský (ÚJV Řež, a. s.)   (Room 5)
Paper
15:30
6.7 Experimental Thermal Hydraulics - Hiroyuki Ohshima (Japan Atomic Energy Agency) Prof. Nikolay Pribaturin (IBRAE RAS, IT SB RAS) (until 17:30) (Room 6)
15:30 Heat transfer and temperature non-uniformities in pin bundles with heavy liquid metal coolant at various spacing ways - Mr Aleksandr Sorokin (SSC RF - IPPE) Julia Kuzina (SSC RF - IPPE)   (Room 6)
Material
15:50 Thermal-hydraulic experiments supporting the MYRRHA fuel assembly - Dr Julio Pacio (Karlsruhe Institute of Technology)   (Room 6)
Material
16:30 NACIE-UP: a HLM loop facility for natural circulation experiments - Ms Morena Angelucci (University of Pisa)   (Room 6)
Material
16:50 Eddy current flowrate and local ultrasonic velocity measurements in liquid sodium - Mr Nico Krauter (Helmholtz-Zentrum Dresden - Rossendorf)   (Room 6)
Paper
15:30
7.3 Non Proliferation Aspects of Fast Reactors -Mr SANG JI KIM (KOREA ATOMIC ENERGY RESEARCH INSTITUTE) Dr Alexander CHEBESKOV (IPPE) (until 17:30) (Room 2)
15:30 Status and perspectives of industrial supply chain for Fast Reactors - Dr Michele Frignani (Ansaldo Nucleare S.p.A.)   (Room 2)
Material
15:50 ASTRID - An original and efficient project organization - Mr Laurent VOLPE (French Atomic Energy Commission)   (Room 2)
Material
16:30 FALCON advancements towards the implementation of the ALFRED Project - Dr Michele Frignani (Ansaldo Nucleare S.p.A.)   (Room 2)
Material
16:50 The GIF Proliferation Resistance and Physical Protection (PR&PP) Evaluation Methodology: Status, Applications and Outlook - Dr Alexander CHEBESKOV (IPPE)   (Room 2)
Material
17:10 Closing Up Nuclear Fuel Cycle In a Two-Component System with Thermal And Fast Neutron Reactors - Mr Oleg Saraev (Russian Federation State Atomic Energy Corporation "Rosatom")   (Room 2)
17:30 --- Coffee Break ---
17:50
Poster Session 2 (until 19:00) ()
17:50 Actual Status of the Development of Multigroup XS Libraries for the Gas-cooled Fast Reactor in Slovakia - Dr Štefan Čerba (Slovak University of Technology in Bratislava)   ()
Material
17:50 Advanced Coupling Methodology for Thermal-hydraulic calculations - Mr JEAN-MARIE HAMY (AREVA NP)   ()
Paper
17:50 Analyses of unprotected transients in GFR (ALLEGRO) and SFR reactors supporting the group constant generation methodology - Mr Bálint Batki (Centre for Energy Research, Hungarian Academy of Sciences)   ()
17:50 Analysis of Irradiation Ability of China Experimental Fast Reactor - Mr Xiaoliang Chen (China Institute of Atomic Energy)   ()
Material
17:50 Analysis of the EBR-II SHRT-45R neutronics benchmark with ERANOS-2.0 - Dr Willem Frederik Geert Van Rooijen (Research Institute of Nuclear Engineering, University of Fukui)   ()
Material
17:50 ANALYSIS OF VARIOUS APPROXIMATIONS IN NEUTRONIC CALCULATIONS OF TRANSIENT IN FAST REACTORS - Mrs Irina Chernova (Nuclear Safety Institute of Russian Academy of Sciences)   ()
Paper
17:50 Application of CFD simulation to validate the BREST-OD-300 primary circuit design - Mr Alexey Tutukin (Vladimirovich)   ()
Material
17:50 Assessment of Creep Damage Evaluation Methods for Grade 91 Steel in the ASME and JSME Nuclear Codes - Dr Tai Asayama (Japan Atomic Energy Agency)   ()
Material
17:50 Basic Visualization Experiments on Eutectic Reaction of Boron Carbide and Stainless Steel under Sodium-Cooled Fast Reactor Conditions - Dr Hidemasa Yamano (Japan Atomic Energy Agency)   ()
Material
17:50 Benchmark Analysis of EBR-II SHRT45R using MARS-LMR - Dr Chiwoong CHOI (Korea Atomic Energy Research Institute (KAERI))   ()
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17:50 Burnup Analysis for BN-600 Reactor Core fueled with MOX fuel and Minor Actinides - Mr Moustafa Aziz Ibrahim (Nuclear and Radiological Regulatory authority)   ()
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17:50 Calculation and Experimental Data Analysis of Neutron Spatial/Energy Distribution in the BOR-60 Blanket - Mr Yury Naboyshchikov (JSC "State Scientific Center - Research Institute of Atomic Reactors")   ()
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17:50 CALCULATION OF NEUTRONIC PARAMETERS IN SUPPORT OF A BOR-60 EXPERIMENTAL FA WITH MODERATING ELEMENTS - Mr Artem Varivtcev (JSC “SSC RIAR”)   ()
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17:50 CFD investigation of thermal-hydraulic characteristics in a SFR fuel assembly - Mr Jae-Ho Jeong (KAERI)   ()
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17:50 Characterization of LBE Non-isothermal Natural Circulation by Experiments with HELIOS Test Loop and Numerical Analyses - Mr Yonghoon Shin (Seoul National University)   ()
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17:50 Comparative analysis of nuclear energy lexicon - Prof. Nikolay Maksimov (National research nuclear university (Moscow Engineering Physics Institute))   ()
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17:50 Computational Analysis Code Development for core and primary system thermal hydraulic design of SFR - Mr Zhiwei Zhou (Engineer)   ()
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17:50 Computational Analysis Code Development for Emergency Heat Removal of Pool-style Fast Reactors - Ms Xiuli Xue (Senior engineer)   ()
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17:50 Concept of multifunctional fast neutron research reactor (MBIR) core with metal (U-Pu-Zr)-fuel - Mr Victor Blandinskiy (NRC "Kurchatov Institute")   ()
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17:50 DEPENDENCE OF INTERMEDIATE HEAT EXCHANGER LIFE ON PRIMARY SODIUM HEATING RATE DURING POWER RAISING - Dr Velusamy K (IGCAR)   ()
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17:50 Design and Fabrication of Closed Loop Systems (CLS) for the Fast Flux Test Facility (FFTF) - Mr David Wootan (Pacific Northwest National Laboratory)   ()
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17:50 DESIGN VALIDATION OF PFBR FUEL SUBASSEMBLY TRANSPORTATION CASK WITH MOCKUP TRIAL RUN - Mr Puthiyavinayagam Pillai (Indira Gandhi Centre for Atomic Research)   ()
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17:50 Detection and analysis of fuel cladding damages using gamma ray spectroscopy - Dr Romain Coulon (CEA LIST)   ()
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17:50 Development and Applications of Nuclear Design and Safety Assessment Program SuperMC for Fast Reactor - Prof. liqin hu (Institute of Nuclear Energy Safety Technology, CAS · FDS Team)   ()
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17:50 Development and Validation of EBRDYN code by Benchmark Analysis of EBR-II SHRT-17 Test - Mr Partha Sarathy UPPALA (IGCAR, INDIA)   ()
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17:50 Development experience for experimental reactor facility cooled vith evaporating liquid metals - Mr Nikolay Loginov (SSC RF-IPPE)   ()
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17:50 Development of innovating Na leak detector on pipes - Ms Marianne GIRARD (CEA/FRANCE)   ()
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17:50 Development of Research Nuclear Power Facility with MBIR Multi-Purpose Fast Neutron Research Reactor - Mr Alexander Tuzov (JSC "SSC RIAR")   ()
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17:50 Development of Safety, Irradiation, and Reliability Databases based on Past U.S. SFR Testing and Operational Experiences - Mr Tanju Sofu (Argonne National Laboratory)   ()
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17:50 EBR-II SHRT-17 and SHRT-45R Benchmark Analyses - Dr Tyler Sumner (Argonne National Laboratory)   ()
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17:50 Evaluation of data and model uncertainties and their effect on the fuel assembly temperature field of the ALFRED Lead-cooled Fast Reactor - Mr Francesco Lodi (University of Bologna)   ()
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17:50 Evaluation of the OECD/NEA/SFR-UAM Neutronics Reactivity Feedback and Uncertainty Benchmarks - Dr Nicolas Stauff (Argonne National Laboratory)   ()
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17:50 EXPERIENCE OF COMMISSIONING OF BN-800 CORE DIAGNOSTIC SYSTEM (SDRU) - Mr Vladimir Danilenko (FSUE «Alexandrov Research Institute of Technology»)   ()
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Poster
17:50 Experiences during construction & Commissioning of electrical power Generation and Evacuation systems in PFBR - Mr Rajan Babu Vinayagamoorthy (Director (Technical))   ()
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17:50 Expriment and Analysis of Flow distribution of MOX Assembly - Mr Huanjun Zhu (CEFR)   ()
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17:50 Features of the physics of the MBIR reactor core - Mr Vladimir Eliseev (SSC RF-IPPE)   ()
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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. - Mr Konstantin Mitrofanov (JSC “SSC RF – IPPE”)   ()
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17:50 Hydraulic Design and Evaluation of the PHTS Mechanical Pump of PGSFR - Dr HUEE-YOUL YE (Korea Atomic Energy Research Institute)   ()
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17:50 Impact of nuclear data uncertainties on the reactivity coefficients of ALFRED - Dr Giacomo Grasso (Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA))   ()
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17:50 Inspection specifications leading to extended ASTRID Design rules - Mr Francois Baque (CEA)   ()
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17:50 INTEGRATED R&D TO VALIDATE INNOVATIVE EMERGENCY HEAT REMOVAL SYSTEM FOR BN-1200 REACTOR - Mr Vasiliy Pakholkov (JSC “Afrikantov OKBM”)   ()
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17:50 Investigation of the homogenization effect in sodium void reactivity in PGSFR - Dr Jong Hyuck Won (KAERI)   ()
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17:50 LES-SIMULATION OF HEAT TRANSFER IN A TURBULENT PIPE - Mr Konstantin Sergeenko (Michailovich)   ()
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17:50 Lessons Learned from Fast Flux Test Facility Experience - Mr David Wootan (Pacific Northwest National Laboratory)   ()
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17:50 LOGOS CFD software application for the analysis of liquid metal coolants in the fuel rod bundles geometries - Dr Dmitry Fomichev (JSC NIKIET)   ()
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17:50 Low-void-effect sodium-cooled core: Uncertainty of local sodium void reactivity as a result of nuclear data uncertainties - Dr Sandro Pelloni (Paul Scherrer Institute)   ()
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17:50 Methodical uncertainty of criticality precise calculations for fast lead reactor - Mrs Varvara Yufereva (JSC «N.A. Dollezhal Research and Developmant Institute of Power Engineering») Ms Ksenia Kalugina (JOINT-STOCK COMPANY «N.A. DOLLEZHAL RESEARCH AND DEVELOPMENT INSTITUTE OF POWER ENGINEERING»)   ()
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17:50 Modeling of Phenix End-of-Life control rod withdrawal tests with the Serpent-DYN3D code system - Dr Emil Fridman (Helmholtz-Zentrum Dresden-Rossendorf)   ()
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17:50 More precise definitions of the perturbation theory formulas for reactivity effects calculations - Mr boris abramov (Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering named after A. I. Leypunsky")   ()
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17:50 NEW NEUTRONIC CALCULATION CODES BASED ON DISCRETE ORDINATES METHOD USING METHODS OF FINITE DIFFERENCES AND FINITE ELEMENTS - Mr Valery Bereznev (IBRAE)   ()
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17:50 Nuclear Reactor Modelling and Simulation Toolkit (NuReMoST) –Numerical Reactor Model Configuration System with Interface to Simulation Codes - Mr Chirayu Batra (IAEA)   ()
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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)   ()
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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 - Mr Evgeny Rozhikhin (IPPE)   ()
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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 - Dr Stefano Monti (IAEA)   ()
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17:50 Participation of Mexico in the OECD/NEA SFR Benchmark using the Monte Carlo code Serpent - Dr Federico Puente Espel (Instituto Nacional de Investigaciones Nucleares)   ()
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17:50 Passive Safety Testing at the Fast Flux Test Facility Relevant to New LMR Designs - Mr David Wootan (Pacific Northwest National Laboratory)   ()
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17:50 PERFORMANCE EVALUATION OF TIN OXIDE BASED SENSOR FOR MONIOTORING TRACE LEVELS OF H2 IN ARGON COVER GAS PLENUM OF FBTR - Mr Balija Sreenivasulu (IGCAR)   ()
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17:50 Potential Capabilities in Transmutation of Minor Actinides of the BOR-60 Reactor and MBIR Reactor under Construction - Mr Igor Zhemkov (JSC “SSC RIAR”)   ()
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17:50 Preliminary Design of Zero Power Reactor for CEFR MOX Core - Mr Qi Zhou (China Institute of Atomic Energy)   ()
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17:50 Research on modeling and simulation of the primary coolant system for China Experimental Fast Reactor - Prof. Zhigang Zhang (Harbin Engineering University)   ()
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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 - Mr Svyatoslav Sikorin (Nikolaevich)   ()
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17:50 Russian Companies’ involvement in CEFR RP (China) construction - Mr Igor Petrov (JSC “Afrikantov OKBM”)   ()
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17:50 Scoping Analysis of STELLA-2 using MARS-LMR - Dr Jewhan Lee (KAERI)   ()
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17:50 SIMMER ANALYSES OF THE EBR-II SHUTDOWN HEAT REMOVAL TESTS - Dr Barbara Vezzoni (Karlsruhe Institute of Technology, Germany)   ()
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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 - Mr Pengrui Qiao (China Institute of Atomic Energy, Beijing, China)   ()
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17:50 System of coordinated calculation benchmarks for a fast reactor with sodium coolant in closed fuel cycle - Mr Mikhail Ternovykh (National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)) Dr Georgy Tikhomirov (National Research Nuclear University MEPhI (Moscow Engineering Physics Institute))   ()
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17:50 The approaches to the radiation characteristics of structural elements of the core determination during operation and decommissioning for BN-type reactors - Mr Mikhail Kriachko (Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Pow