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

Speaker List

• boris abramov
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    More precise definitions of the perturbation theory formulas for reactivity effects calculations

• Evgeny Adamov
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    Closed fuel cycle technologies based on fast reactors as the corner stone for sustainable development of nuclear power

• Evgeny Adamov
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    Knowledge Transfer and Management for an active fleet of fast reactors

• Alexander Aerts
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    The Conditioning and Chemistry Programme for MYRRHA

• Pietro Agostini
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    Towards a new approach for structural materials of Lead Fast Reactors

• Kosuke Aizawa
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    Development of under sodium viewer for next generation sodium-cooled fast reactor

• Viktor Alekseev
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    Investigation of steel corrosion products mass transfer in sodium

• Alessandro Alemberti
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    Status of Generation-IV Lead Fast Reactor Activities

• RUDOLF ALEXAKHIN
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    ECOLOGICAL ASPECTS OF THE USE OF FAST REACTORS IN A CLOSED NUCLEAR FUEL CYCLE UNDER THE “PRORYV” PROJECT

• Yukiya Amano (IAEA)
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    Opening Address by Director General, IAEA (by video message)

• Andrei Andrianov
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    Performance and sustainability assessment of nuclear energy deployment scenarios with fast reactors: advanced tools and application

• Olga Andrianova
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    INTEGRAL EXPERIMENTS WITH MINOR ACTINIDES AT THE BFS CRITICAL FACILITIES: STATE-OF-THE-ART SURVEY, REEVALUATION AND APPLICATION

• Artem Anfimov
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    ARRANGEMENT OF THE BN-600 REACTOR CORE REFUELING AT TRANSITION TO THE INCREASED FUEL BURN-UP

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    Safety Assurance for BN-1200 Power Unit During Accidents

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    Specific features of BN-1200 core in case of use of nitride or MOX fuel

• Morena Angelucci
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    NACIE-UP: a HLM loop facility for natural circulation experiments

• Pavel Antipin
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    PROBABILISTIC SAFETY ANALYSIS RESULTS FOR BN REACTOR POWER UNITS

• Mitsuhiro Aoyagi
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    Identification of important phenomena under sodium fire accidents based on PIRT process

• Venkatesan Arasappan
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    3D Modeling of Fuel Handling System for PFBR Operator Training Simulator

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    Development and Deployment of Knowledge Management Portal for Fast Breeder Reactors

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    Design modifications of Instrumentation & Control System of future FBRs

• Kazuo Arie
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    Innovative TRU Burning Fast Reactor Cycle Using Uranium-free TRU Metal Fuel - Core Design Progress -

• Vladimir Artisyuk
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    Analysis of the SVBR-100 nuclear fuel cycle by means of the advanced nuclear fuel cycle assessment methodology (ATTR)

• Bhaduri Arun Kumar
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    Indian Fast Reactor Programme : Status and R&D Achievements

• Tai Asayama
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    Development of core and structural materials for fast reactors

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    Assessment of Creep Damage Evaluation Methods for Grade 91 Steel in the ASME and JSME Nuclear Codes

• Iurii Ashurko
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    Russian SFR Safety Requirements and Approaches and Their Correspondence to Generation-IV SFR Safety Design Criteria (Russia)

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    DECAY HEAT REMOVAL SYSTEM IN THE SECONDARY CIRCUIT OF THE SODIUM-COOLED FAST REACTOR AND EVALUATION OF ITS CAPACITY

• Radomir Askhadullin
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    Strategies of maintaining appropriate technology of heavy liquid metal coolants in advanced nuclear power plants

• Osvaldo Azpitarte
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    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)

• Andrey Balanin
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    Physical and technical basics of the concept of a competitive gas cooled fast reactor facility with the core based on coated fuel microparticles

• Francois Baque
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    Inspection specifications leading to extended ASTRID Design rules

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    R&D status on in-sodium ultrasonic transducers for ASTRID inspection

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    Main R&D objectives and results for under-sodium inspection carriers – Example of the ASTRID matting exceptional inspection carrier.

• dominique barbier
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    Main operation procedures for ASTRID gas power conversion system

• Svetlana Barsanova
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    Change in Mechanical Properties of Spent Fast Reactor Claddings

• Mikhail Baryshnikov
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    The Commercial Potential of the Dual-Component Nuclear Power System

• Ethan BATES
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    Conclusions of a Benchmark Study on the EBR-II SHRT-45R Experiment

• Bálint Batki
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    Analyses of unprotected transients in GFR (ALLEGRO) and SFR reactors supporting the group constant generation methodology

• Chirayu Batra
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    Introduction to the YGE Panel

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    The Role of the IAEA in Fast Reactor Development and Knowledge Transfer

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    Nuclear Reactor Modelling and Simulation Toolkit (NuReMoST) –Numerical Reactor Model Configuration System with Interface to Simulation Codes

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    IAEA’s Fast Reactors Knowledge Portals and Catalogues

• stephane Beils
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    CFD Simulation of Corium / Materials Interaction for Severe Accidents

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    “ASTRID safety design: Radiological confinement improvements compared to previous SFRs”

• Heather Bell (U.S. Department of Energy)
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    Overview of U.S. Fast Reactor Technology R&D Program

• Mikhail Belonogov
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    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

• Alexander Belov
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    Detailed engineering neutron codes for calculations of fast breeder reactors

• Sergey Belov
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    OPERABILITY VALIDATION OF FUEL PINS WITH CLADDINGS MADE OF EK164-ID STEEL IN THE BN-600 REACTOR

• Ladislav Bělovský
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    Helium Recovery from Guard Vessel Atmosphere of the ALLEGRO Reactor

• Michael Benson
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    Controlling FCCI with Pd in metallic fuel

• Valery Bereznev
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    NEW NEUTRONIC CALCULATION CODES BASED ON DISCRETE ORDINATES METHOD USING METHODS OF FINITE DIFFERENCES AND FINITE ELEMENTS

• Frédéric BERTRAND
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    Status of severe accident studies at the end of the conceptual design: feedback on mitigation features

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

• Edouard Bissen (CEA)
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    Passive Complementary Safety Devices for ASTRID severe accident prevention

• Dmitry Blagodatskykh
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    ROUZ CODE: CFD APPROACH FOR ASSESSMENT OF RADIATION SITUATION DURING ATMOSPHERE RADIOACTIVITY RELEASES WITHIN AN INDUSTRIAL SITE

• Victor BLANC
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    Fuel Melting Margin Assessment of Fast Reactor Oxide Fuel Pins using a Statistical Approach

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    Conceptual design of fuel and radial shielding sub-assemblies for ASTRID

• Victor Blandinskiy
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    Concept of multifunctional fast neutron research reactor (MBIR) core with metal (U-Pu-Zr)-fuel

• Martine BLAT YRIEIX
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    Stainless Steels Corrosion in Sodium Fast Reactor: Feedback from Risks during Maintenance Operations (SCC in Caustic Solution and Intergranular Corrosion by Acid Solution)

• Vladimir Bobrovskii
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    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

• Aleksey Bochkarev
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    SFR INHERENT SAFETY FEATURES AND CRITERIA ANALYSIS

• Sandra Bogetic
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    3-D Core Design of the TRU-Incinerating Thorium RBWR Using Accident Tolerant Cladding

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

• Leonid Bolshov
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    Concluding Report on the Technical Sessions

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    Safety assurance of the new generation of the Russian fast liquid metal reactors

• Sara Bortot
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    A proposal for a pan-European E&T programme supporting the development and deployment of ALFRED

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    Preliminary Safety Performance Assessment of ESFR CONF-­2 Sphere-­pac‐Fueled Core

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    Design of a nitride-­fueled lead fast reactor for MA transmutation

• Laural Briggs
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    EBR-II Passive Safety Demonstration Tests Benchmark Analyses

• Acacia Brunett
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    U.S. Sodium Fast Reactor Codes and Methods: Current Capabilities and Path Forward

• Andrey Buchatsky
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    PREDICTION OF CREEP-RUPTURE PROPERTIES FOR AUSTENITIC STAINLESS STEELS UNDERGONE NEUTRON IRRADIATION AT DIFFERENT TEMPERATURES

• Matthew Bucknor
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    An Assessment of Fission Product Scrubbing in Sodium Pools Following a Core Damage Event in a Sodium Cooled Fast Reactor

• emilie buravand
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    First assessment of a digestion method applied to recover plutonium from refractory residues after dissolving spent SFR MOX fuel in nitric acid

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    A comprehensive study of the dissolution of spent SFR MOX fuel in boiling nitric acid (the PHENIX NESTOR-3 case)

• Kirill Butov
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    Industrial Exploitation of Testing Ground for Treatment of Radwaste of Alkaline Coolants under Decommissioning of Fast Research Reactors

• William Carmack
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    Overview of the U.S. DOE fast reactor fuel development program

• Štefan Čerba
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    Actual Status of the Development of Multigroup XS Libraries for the Gas-cooled Fast Reactor in Slovakia

• Ruslan Chalyy
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    SOCRAT-BN integral code for safety analysis of NPP with sodium cooled fast reactors: development and plant applications

• FREDERIC CHANTECLAIR
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    ASTRID reactor: design overview and main innovative options for Basic Design

• Alexander Chebeskov
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    Fast Neutron Reactors, Fuel Cycles and Problem of Nuclear Non-Proliferation

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    The GIF Proliferation Resistance and Physical Protection (PR&PP) Evaluation Methodology: Status, Applications and Outlook

• Xiaoliang Chen
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    Analysis of Irradiation Ability of China Experimental Fast Reactor

• Xue-Nong Chen
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    Possibility studies of a boiling water cooled traveling wave reactor

• Irina Chernova
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    ANALYSIS OF VARIOUS APPROXIMATIONS IN NEUTRONIC CALCULATIONS OF TRANSIENT IN FAST REACTORS

• Subhash Chander CHETAL
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    Fast Reactor Development and International Cooperation (by Honorary General Chair)

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    Safety criteria for future Indian SFRs (India)

• Hual-Te Chien
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    Development and Demonstration of Ultrasonic Under-Sodium Viewing System for SFRs

• Chiwoong CHOI
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    Benchmark Analysis of EBR-II SHRT45R using MARS-LMR

• Mikhail Chudakov (IAEA)
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    Closing Remarks by Conference General Co-Chair

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    Welcome Note by Conference General Co-Chair

• Vladimir Chudanov
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    Applications of the DNS CONV-3D Сode for Simulations of Liquid Metal Flows

• Luciano Cinotti
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    Simplification, the atout of LFR-AS-200

• Stéphanie Cornet
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    Overview of the Nuclear Energy Agency Scientific Activities on Advanced Fuel Cycles

• Didier Costes
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    Resting Bottom Fast Reactor

• Romain Coulon
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    Detection and analysis of fuel cladding damages using gamma ray spectroscopy

• ARNAUD COURCELLE
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    TEM CHARACTERIZATION OF A SWELLING-RESISTANT AUSTENITIC STEEL IRRADIATED AT HIGH TEMPERATURE (>600°C) IN THE PHENIX FAST REACTOR

• Theodore COZZIKA
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    Chemical compatibility with liquid sodium after in service solicitations: feedback on stainless steel in French sodium Fast reactor after 35 years of operation

• Nicolas Crepin
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    Study of isolation valve for Sodium Fast Reactor

• Vladimir Danilenko
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    EXPERIENCE OF COMMISSIONING OF BN-800 CORE DIAGNOSTIC SYSTEM (SDRU)

• Petr Dařílek
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    ALLEGRO Core Neutron Physics Studies

• Yann DE CARLAN
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    Use of ion irradiations to help design of advanced austenitic steels

• FRANCK DECHELETTE
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    ASTRID FUEL HANDLING ROUTE FOR THE BASIC DESIGN

• Viktor Dekusar
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    COMPARATIVE ANALYSIS OF ELECTRICITY GENERATION FUEL COST COMPONENT AT NPPs WITH WWER AND BN-TYPE REACTOR FACILITIES

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    FEATURES OF THE NUCLEAR FUEL CYCLE SYSTEMS BASED ON JOINT OPERATION OF FAST AND THERMAL REACTORS

• Martin Delmas
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    Study of isolation valve for Sodium Fast Reactor

• Edmundo del Valle Gallegos
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    Solution of the OECD/NEA SFR Benchmark with the Mexican neutron diffusion code AZNHEX

• Alexander Denisov
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    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

• Matthew Denman
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    Development of the U.S. Sodium Component Reliability Database

• norihiro doda
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    Numerical Analysis of EBR-II Shutdown Heat Removal Test-17 using 1D Plant Dynamic Analysis Code coupled with 3D CFD Code

• Yrii Drobyshev
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    Analysis of the Characteristics of the Fast Breeder Reactor with Metallic Fuel

• Konstantin Dvoeglazov
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    The actinide oxides preparation by thermal denitration

• Dmitry Dzama
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    THE CODE ROM FOR ASSESSMENT OF RADIATION SITUATION ON A REGIONAL SCALE DURING ATMOSPHERE RADIOACTIVITY RELEASES

• Vladimir Eliseev
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    Features of the physics of the MBIR reactor core

• Dongjin EUH
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    Development of Flow Identification Technology for the PGSFR Thermal Fluidic Design Validation

• Thomas Fanning
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    Uncertainty Quantification of EBR-II Loss of Heat Sink Simulations with SAS4A/SASSYS-1 and DAKOTA

• Concetta Fazio
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    Materials corrosion in Fast Reactor environment

• Rafael Fernandez
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    The evolution of the primary system design of the MYRRHA facility

• Randall Fielding
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    Americium Retention During Metallic Fuel Fabrication

• Anton Filanovich
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    Thermal and elastic properties of CexTh1-xO2 mixed oxides: a self-consistent thermodynamic approach

• Philippe Filliatre
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    Dependability of the fission chambers for the neutron flux monitoring system of the French GEN-IV SFR

• MIchael Flad
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    Quantitative Evaluation of the Post Disassembly Energetics of a Hypothetical Core Disruptive Accident in a Sodium Cooled Fast Reactor

• Dmitry Fomichev
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    LOGOS CFD software application for the analysis of liquid metal coolants in the fuel rod bundles geometries

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    Numerical simulation of hydraulics and heat transfer in the BREST-OD-300 LFR fuel assembly

• E. Fridman
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    Modeling of Phenix End-of-Life control rod withdrawal tests with the Serpent-DYN3D code system

• Michele Frignani
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    FALCON advancements towards the implementation of the ALFRED Project

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    Status and perspectives of industrial supply chain for Fast Reactors

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    Fast Reactors and Nuclear Cogeneration: A Market and Economic Analysis

• János Gadó
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    The ALLEGRO experimental Gas Cooled Fast Reactor Project

• Augusto Gandini
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    Recent and Potential Advances of the HGPT methodology

• Fuhai Gao
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    The development of a computer code for predicting fast reactor oxide fuel element thermal and mechanical behavior (FIBER-Oxide)

• Roger GARBIL
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    'EURATOM SUCCESS STORIES’ IN FACILITATING PAN-EUROPEAN E&T COLLABORATIVE EFFORTS

• Francois GAUCHE
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    Overview of GEN-IV International Forum Activities. Status and Prospects of Fast Reactors

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

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    Sensitivity studies of SFR unprotected transients with global neutronic feedback coefficients

• Jean-Baptiste GENIN
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    OSCAR-Na validation against sodium loop experiments

• Delphine Gérardin
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    Design Evolutions of the Molten Salt Fast Reactor

• Gunter Gerbeth
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    The DRESDYN project: A new facility for thermohydraulic studies with liquid sodium

• Thierry GERVAIS
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    (U,Pu)O2-x MOX pellet for Astrid reactor project

• Zohreh Gholamzadeh
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    Computational investigation of nuclear waste incineration efficiency in a subcritical molten salt driven by 50-100 MeV protons

• Grasso Giacomo
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    A safe and competitive lead-cooled small modular fast reactor concept for a short-term deployment

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    The core of the LFR-AS-200: robustness for safety

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    Impact of nuclear data uncertainties on the reactivity coefficients of ALFRED

• Marianne GIRARD
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    Development of innovating Na leak detector on pipes

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    Testing of electrochemical hydrogen meter in a sodium facility in Cadarache

• NATHALIE GIRAULT
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    Main outcomes from the JASMIN project: development of ASTEC-Na for severe accident simulation in Na cooled fast reactors

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

• Jean-Paul Glatz
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    The European Commission contribution to the development of safe and sustainable fast reactor systems

• Andrei Glazov
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    On-site nuclear fuel cycle of “BREST” reactors

• Natalia Glushkova
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    Examination of ChS-68 Steel Used as a BN-600 Reactor Cladding Material

• Oleg Golosov
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    Thermal Annealing Effect on Recovery of Corrosion Properties of EP-450 Steel Irradiated IN BN-600 Reactor to High Damage Doses

• Iulian Golovchenko
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    EXPERIENCE AND APPLICABILITY OF HIGH DENSE METAL URANIUM IN ADVANCED BN-REACTORS

• Armando Miguel Gomez Torres
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    Verification of the neutron diffusion code AZNHEX by means of the Serpent-DYN3D and Serpent-PARCS solution of the OECD/NEA SFR Benchmark

• Yannick Gorsse (CEA-Saclay)
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    Development and Validation of Multi-scale Thermal-Hydraulics Calculation Schemes for SFR Applications at CEA

• Marc Gosset
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    Study of isolation valve for Sodium Fast Reactor

• David Grabaskas
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    A Mechanistic Source Term Calculation for a Metal Fuel Sodium Fast Reactor

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    Advanced Reactor PSA Methodologies for System Reliability Analysis and Source Term Assessment

• Christopher Grandy
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    FASTER Test Reactor Preconceptual Design

• Dmitriy Gremyachkin
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    Validation of the evaluated fission product yields data from the fast neutron induced fission of 235U, 238U, 239Pu

• Jean-Paul Grouiller
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    Pu recycling capabilities of ASTRID reactor

• Bernard GUILLOU
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    ASTRID hot cells

• Andrey Gulevich
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    Justification of arrangement, parameters, and irradiation capabilities of the MBIR reactor core at the initial stage of operation

• Máté Gergely Halász
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    Fuel cycle studies of Generation IV fast reactors with the SITON v2.0 code and the FITXS burn-up scheme

• Jean-Marie HAMY
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    Advanced Coupling Methodology for Thermal-hydraulic calculations

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    Status of ASTRID Nuclear Island Design and Future Trends

• Benjamin Hary
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    Optimization of the thermomechanical treatment to achieve a homogeneous microstructure in a 14Cr ODS steel

• Hiroki Hayafune
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    Advanced sodium-cooled fast reactor development regarding GIF safety design criteria

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    Current status of GIF collaborations on sodium-cooled fast reactor system

• Florent Heidet
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    Neutron Thermalization in the FASt TEst Reactor

• Jaeseok Heo
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    Sensitivity and Uncertainty Analysis in Best-Estimate modeling for PGSFR Under ULOF Transient

• Shun Hirooka
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    Mechanical and Thermal Properties of (U,Pu)O2-x

• Boris Hombourger
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    On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors

• Jonggan Hong
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    Thermal Hydraulic Study of Steam Generator of PGSFR

• liqin hu
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    Development and Applications of Nuclear Design and Safety Assessment Program SuperMC for Fast Reactor

• Yun HU
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    Study on the sensitivity analysis of the installed capacity and the high-level waste generation based on closed nuclear fuel cycle

• qunying huang
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    Strategy and R&D status of China Lead-based Reactor

• Xingkai Huo
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    Physical start-up test of China Experimental Fast Reactor

• Moustafa Aziz Ibrahim
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    Burnup Analysis for BN-600 Reactor Core fueled with MOX fuel and Minor Actinides

• Kazumi IKEDA
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    Feasibility of MA Transmutation by (MA, Zr)Hx in Radial Blanket Region of Fast Reactor and Plan of Technology Development

• Tomoko Ishizu
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    Model validation of the ASTERIA-FBR code related to core expansion phase based on THINA experimental results

• T. Ivanova
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    Benchmark Evaluation of Dounreay Prototype Fast Reactor Minor Actinide Depletion Measurements

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    Overview of NEA Activities Related to Fast Reactors

• Mikhail Ivochkin
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    Probabilistic Safety Analysis of NPP with BREST-OD-300 reactor

• Alexey Izhutov
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    BOR-60 REACTOR OPERATIONAL EXPERIENCE AND EXPERIMENTAL CAPABILITIES

• KODANDARAMAN J
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    Concurrent Trends in Indian Fast Reactor Fuel Reprocessing Programme

• Robert Jacqmin
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    Analysis of the BFS-115-1 experiments

• Denis Janin
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    Introduction to the Workshop

• Maria Laura Japas
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    Density of sodium along the Liquid-Vapor Coexistence Curve, including the Critical Point

• Marti Jeltsov
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    SEISMIC SLOSHING EFFECTS IN LEAD-COOLED FAST REACTORS

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    VOIDING OF ELSY PRIMARY SYSTEM DURING STEAM GENERATOR LEAKAGE

• Colby Jensen
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    Review of Transient Testing of Fast Reactor Fuels in the Transient REActor Test Facility (TREAT)

• Jae-Ho Jeong
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    CFD investigation of thermal-hydraulic characteristics in a SFR fuel assembly

• Ksenia Kalugina (JOINT-STOCK COMPANY «N.A. DOLLEZHAL RESEARCH AND DEVELOPMENT INSTITUTE OF POWER ENGINEERING»)
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    Methodical uncertainty of criticality precise calculations for fast lead reactor

• Hideki Kamide
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    Concluding Report on the Technical Sessions

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    Knowledge Transfer and Management during long outage periods

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    Progress of Design and related Researches of Sodium-cooled Fast Reactor in Japan

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

• Aydin Karahan
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    Validation of Advanced Metallic Fuel Models of SAS4A using TREAT M-Series Overpower Test Simulations

• Velusamy Karuppanna Gounder
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    Steady State Modelling and Validation of Once Through Steam Generator

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    Computational modeling of flow blockage in fuel subassemblies and molten material relocation in sodium cooled fast reactors

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    Computational modelling of inter-wrapper flow and primary system temperature evolution in FBTR under extended Station Blackout

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    DEPENDENCE OF INTERMEDIATE HEAT EXCHANGER LIFE ON PRIMARY SODIUM HEATING RATE DURING POWER RAISING

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    Numerical and Experimental Investigations of Tube-to-Tube Interaction of Air Heat Exchangers of PFBR under Seismic Excitations

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    Thermal hydraulic investigation of sodium fire and hydrogen production in top shield enclosure of an FBR following a core disruptive accident

• Yury Khomyakov
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    Minimisation of Reactivity Margin for Equilibrium Core of Liquid Metal Cooled Fast Reactors

• Ju-Seong Kim
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    Fuel Cladding Chemical Interaction Tests of Irradiated Metallic Fuel

• Hyungmo Kim
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    Heat Transfer Performance Test for a Sodium-to-Air Heat Exchanger with an Inclined Finned-Tube Banks

• Yonghee Kim
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    Feasibility and Challenges for Self-sustainable Long-Life SMR without Refueling

• Myung Hyun Kim
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    Performance Analysis of Various Thorium Fuel Options for the Sodium Cooled Fast Reactor

• Nak Hyun Kim
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    High temperature design and evaluation of forced draft sodium-to-air heat exchanger in PGSFR

• Sung Ho Kim
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    Fabrication and Evaluation of Advanced Cladding Tube for PGSFR

• Chihyung Kim
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    Neutronic Self-sustainability of a Breed-and-Burn Fast Reactor Using Super-Simple Fuel Recycling

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    Optimization of Passive Safety Devices FAST and SAFE for Sodium-cooled Fast Reactors

• Evgenii Kinev
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    POSTREACTOR STATE OF THE STANDARD AND EXPERIMENTAL BN-600 FUEL KINDS

• Dmitriy Klinov
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    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

• Lev Kochetkov
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    Development of Fast Reactors in the USSR and the Russian Federation; Malfunctions and Incidents in the Course of their Operation and Solution of Problems.

• Ivan A. Kodeli
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    Uncertainty Analysis of Kinetic Parameters for Design, Operation and Safety Analysis of SFRs

• Gennady Kolotkov
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    Remote detection of raised radioactivity in emission from Beloyarsk nuclear power plant

• Igor Konovalov
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    The behavior features of fuel elements with nitride fuel - theory and experiment

• Yaroslav Kotov
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    Application of Heterogeneous Fuel Assemblies in the Core of Modular Fast Sodium Reactor

• Alexander Kozlov
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    Examination of Fast Reactor Materials and Structural Elements at JSC “INM” Premises

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    Modeling of Processes in Austenitic Steel Produced Under Irradiation in Fast Reactors and Possibilities of Model Practical Application

• N. Krauter
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    Eddy current flowrate and local ultrasonic velocity measurements in liquid sodium

• Jiri Krepel
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    Comparison of fast reactors performance in the closed U-Pu and Th-U cycle

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    Eligibility of Small Molten Salt Fast Reactor (S-MSFR)

• Mikhail Kriachko
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    The approaches to the radiation characteristics of structural elements of the core determination during operation and decommissioning for BN-type reactors

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    The method of calculating tritium content in various technological media of BN-type reactors

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    The study of U-232 accumulation in reprocessed uranium for fast reactor fuel cycle

• Vladimir Kriventsev
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    Report on Panel 1: Safety Design Guidelines

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    IAEA’s Coordinated Research Project on EBR-II Shutdown Heat Removal Tests: An Overview

  • Speaker at

    Overview of the IAEA Activities in the Field of Fast Reactor Technology Development: Current State and Future Vision

  • Speaker at

    Source Term Estimation for Radioactivity Release under Severe Accident Scenarios in Sodium cooled Fast Reactors

• Vladimir Krotov
  • Speaker at

    The UO2– MeO2 (Me = Th, Pu, Zr) cathode crystalline deposits formation during the melts electrolysis.

• Alexey Krylov
  • Speaker at

    SIBYLLA CODE: ASSESSMENT OF WATER BODIES CONTAMINATION AND DOSES RECEIVED BY POPULATION DUE TO RADIOACTIVITY DISCHARGES INTO THE HYDROSPHERE

• Shigenobu Kubo
  • Speaker at

    Study on Safety Design Concept for future Sodium-cooled Fast Reactors in Japan

• Julia Kuzina
  • Speaker at

    Heat transfer and temperature non-uniformities in pin bundles with heavy liquid metal coolant at various spacing ways

• Artem Kuznetsov
  • Speaker at

    BN-800 core with MOX fuel

  • Speaker at

    SELECTION OF A LAYOUT FOR THE BN-800 REACTOR HYBRID CORE

• Sureshkumar KV
  • Speaker at

    Fission product and swelling behaviour in FBTR mixed carbide fuel

  • Speaker at

    Extending the grid plate life - Incorporation of lower axial shield for FBTR

  • Speaker at

    OPERATING EXPERIENCE OF FBTR

  • Speaker at

    Safety Upgradation of Fast Breeder Test Reactor

• Marc LAINET
  • Speaker at

    Current status and progression of GERMINAL fuel performance code for SFR oxide fuel pins

• David LALLEMAND
  • Speaker at

    Recent suppling of 316L(N) stainless steel products for ASTRID

• Julien Large
  • Speaker at

    Study of isolation valve for Sodium Fast Reactor

• Christian Latge
  • Speaker at

    Knowledge Transfer and Management with interrupted development

• Luke LEBEL
  • Speaker at

    Learning from 1970 and 1980-Era Sodium Fire Experiments

• Luke Lebel (Institut de Radioprotection et de Sûreté Nucléaire)
  • Speaker at

    How the Next Generation of People will shape the Next Generation of Nuclear

• KWI LIM LEE
  • Speaker at

    An assessment of transient over-power accident in the PGSFR

• Jeonghyeon Lee
  • Speaker at

    The Effect of Proton Irradiation on the Corrosion Behaviors of Ferritic/Martensitic Steel

• Jewhan Lee
  • Speaker at

    Scoping Analysis of STELLA-2 using MARS-LMR

• Deokjung Lee
  • Speaker at

    Evaluation of Anticipated Transient without Scram for SM-SFR using SAS4A/SASSYS-1

• Aleksandr Legkikh
  • Speaker at

    Methods of controlling concentration of oxygen dissolved in heavy liquid metal coolants (lead and lead-bismuth) of nuclear reactors and test facilities

• David Lemasson
  • Speaker at

    Benchmark Between EDF And IPPE On The Behavior Of Low Sodium Void Reactivity Effect Sodium Fast Reactor During An Unprotected Loss Of Flow Accident

• Vadim Lemekhov
  • Speaker at

    BREST-OD-300 REACTOR FACILITY. DEVELOPMENT STAGES AND JUSTIFICATION

• Song LI
  • Speaker at

    Thermal design of double helium gas gap conduction test facility

• Meimei Li
  • Speaker at

    Sodium compatibility of Recently-Developed Optimized Grade 92 and its Weldments for Advanced Fast Reactors

• Alexey Likhachev (ROSATOM)
  • Speaker at

    Opening Address by Director General, ROSATOM (by video message)

• Andrey Lizin
  • Speaker at

    Research and Pilot Fast Neutron Reactors in Russian Federation as the Ground for Development of Worldwide Commercial Technologies

  • Speaker at

    SELECTION OF CARRIER SALT FOR MOLTEN SALT FAST REACTOR

• Francesco Lodi
  • Speaker at

    Evaluation of data and model uncertainties and their effect on the fuel assembly temperature field of the ALFRED Lead-cooled Fast Reactor

  • Speaker at

    Extension to Heavy Liquid Metal coolants of the validation database of the ANTEO+ sub-channel code

• Nikolay Loginov
  • Speaker at

    Development experience for experimental reactor facility cooled vith evaporating liquid metals

• Denis Lorenzo
  • Speaker at

    INSERTION RELIABILITY STUDIES FOR THE RBC-TYPE CONTROL RODS IN ASTRID

• David Louie
  • Speaker at

    IMPLEMENTATION STATUS OF CONTAIN-LMR SODIUM CHEMISTRY MODELS INTO MELCOR 2.1

• Dmitry Lukyanov
  • Speaker at

    EXPERIENCE OF COMMISSIONING OF THE SECTORAL MONITORING TIGHTNESS SYSTEM OF FUEL ELEMENTS CLADDINGS (SSKGO) OF RF BN-600, RF BN-800

• Jakub Lüley
  • Speaker at

    Assessment of the reactivity effects of Gas cooled Fast Reactor

• María Luppo
  • Speaker at

    Isothermal transformation austenite-ferrite in a P92 steel

  • Speaker at

    New results on the continuous cooling behavior of an ASTM A335 P92 steel

  • Speaker at

    Precipitate phases in a weldment of P92 steel

  • Speaker at

    Study of the austenitization process in a P91 steel

• Edwin Lyman
  • Speaker at

    External Assessment of the U.S. Sodium-Bonded Spent Fuel Treatment Program

• Seiichiro Maeda
  • Speaker at

    Current Status of Next Generation Fast Reactor Core & Fuel Design and Related R&D in Japan

• Inga Makeyeva
  • Speaker at

    Modeling technologies of fuel cycles

• Nikolay Maksimov
  • Speaker at

    Comparative analysis of nuclear energy lexicon

• Gennady Manturov
  • Speaker at

    System of Codes and Nuclear Data for Neutronics Calculations of Fast Reactors and Uncertainty Estimation

• Boris Margolin
  • Speaker at

    Basic principles for lifetime and structural integrity assessment of BN-600 and BN-800 fast reactors components with regard for material degradation

• Evgenii Marinenko
  • Speaker at

    PROBLEMS OF CALCULATION MODELLING OF NITRIDE FUEL PERFORMANCE: DRAKON CODE

• THORSTEN MARLAUD
  • Speaker at

    Recent suppling of 316L(N) stainless steel products for ASTRID

• Elena Marova
  • Speaker at

    Evaluation results of BN-1200 compliance with the requirements of GENERATION IV and INPRO

• Nikolay Maslov
  • Speaker at

    Improving inherent safety BN-800 by the use of fuel assembly with (U, Pu)C microfuel.

• Pavel Maslov
  • Speaker at

    On the possibility of using various types of fuel in the MBIR reactor core

• GILLES MATHONNIERE
  • Speaker at

    How to take into account the fleet composition in order to evaluate Fast Breeder Competitiveness

• Taku Matsumoto
  • Speaker at

    Thermal conductivity of non-stoichiometric (Pu0.928Am0.072)O2-x

• Christopher Matthews
  • Speaker at

    BISON for Metallic Fuels Modeling

• Bruno Merk
  • Speaker at

    A Demand Driven Way of Thinking Nuclear Development – Neutron Physical Feasibility of a Reactor Directly Operating SNF from LWR

• Bruno MICHEL
  • Speaker at

    3D SIMULATION IN THE PLEIADES SOFTWARE ENVIRONMENT FOR SODIUM FAST REACTOR FUEL PIN BEHAVIOR UNDER IRRADIATION

• Ignas Mickus
  • Speaker at

    Preliminary transient analyses of SEALER

• Konstantin Mikityuk
  • Speaker at

    Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow

  • Speaker at

    ESFR-SMART: new Horizon-2020 project on SFR safety

  • Speaker at

    GEN IV Education and Training Initiative via Public Webinars

• Seyed Mohammad Mirvakili
  • Speaker at

    Computational investigation of nuclear waste incineration efficiency in a subcritical molten salt driven by 50-100 MeV protons

• SUDHIR MISHRA
  • Speaker at

    CHALLENGES IN THE FABRICATION AND RECYCLING OF MIXED CARBIDE FUEL

• Konstantin Mitrofanov
  • Speaker at

    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.

  • Speaker at

    The relative yields and half-lives of precursors of delayed neutrons in the fission 241Am by fast neutrons.

• Alexander Moiseev
  • Speaker at

    Welcome Note by Deputy Presidential Envoy in the Ural Federation District

• Nikolay Molokanov
  • Speaker at

    Equipment cost estimation for pilot demonstration lead-cooled fast-neutron reactor BREST-OD-300

  • Speaker at

    The Computer model for the economic assessment of NPP pilot demonstration energy complex with BREST-OD-300 reactor (REM Proryv Project)

• David Montagnier
  • Speaker at

    Study of isolation valve for Sodium Fast Reactor

• Stefano Monti
  • Speaker at

    Report on Panel 2: Small and Medium sized fast reactors

  • Speaker at

    Overview of the international cooperation and collaboration activities initiated and performed under the Technical Working Group on Fast Reactors in last 50 years

• Kyoichi Morimoto
  • Speaker at

    The influence of porosity on thermal conductivity of low-density uranium oxide.

• Koji Morita
  • Speaker at

    The Status of Safety Research in the Field of Sodium-cooled Fast Reactors in Japan

• Nastasia Mosunova
  • Speaker at

    Coupled calculations for the fast reactors safety justification with the EUCLID/V1 integrated computer code

• Olga Myazdrikova
  • Speaker at

    Modeling of hydrodynamic processes at a large leak of water into sodium in the fast reactor coolant circuit

• Yury Naboyshchikov
  • Speaker at

    Calculation and Experimental Data Analysis of Neutron Spatial/Energy Distribution in the BOR-60 Blanket

• Ryodai Nakai
  • Speaker at

    The Safety Design Guideline Development for Generation-IV SFR Systems (Japan/GIF)

• B.K. Nashine
  • Speaker at

    Development of Electromagnetic Devices for Sodium Cooled Fast Reactor Application

• Krishnamurti Natesan
  • Speaker at

    Code Qualification Plan for an Advanced Austenitic Stainless Steel, Alloy 709, for Sodium Fast Reactor Structural Applications

• Laetitia NICOLAS (AREVA)
  • Speaker at

    Recent suppling of 316L(N) stainless steel products for ASTRID

• Evgeniya Nikitina
  • Speaker at

    CORROSION OF 12X18H10T STEEL IN Ce-, Nd- AND U-CONTAINING MOLTEN LiCl-KCl EUTECTIC

• Mikhail Noskov
  • Speaker at

    PERSONNAL TRAINING FOR THE "PRORYV" PROJECT AT THE SEVERSK TECHNOLOGICAL INSTITUTE OF NRNU MEPHI

• Yuriy Nosov
  • Speaker at

    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

• Olga Novichkova
  • Speaker at

    A new generation steel for heat exchangers tubes of reactors design with lead coolant

• Toru Obara
  • Speaker at

    Feasibility of Burning Wave Fast Reactor Concept with Rotational Fuel Shuffling

• Mikołaj Oettingen
  • Speaker at

    TRANSMUTATION TRAJECTORY ANALYSIS IN THE MODELLING OF LFR FUEL CYCLE

• hiroyuki Ohshima
  • Speaker at

    Numerical Simulation Method of Thermal Hydraulics in Wire-wrapped Fuel Pin Bundle of Sodium-cooled Fast Reactor

• Yasushi Okano
  • Speaker at

    The Safety Design Criteria Development and Summary of Its Update for the Generation-IV SFR Systems (USA/Japan/GIF)

• Mikhail Orlov
  • Speaker at

    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

• Yurij Osheyko
  • Speaker at

    The concept of 50-300 MWe modular-transportable nuclear power plant with sodium coolant and a gas turbine

• Julio Pacio
  • Speaker at

    Thermal-hydraulic experiments supporting the MYRRHA fuel assembly

• Vasiliy Pakholkov
  • Speaker at

    INTEGRATED R&D TO VALIDATE INNOVATIVE EMERGENCY HEAT REMOVAL SYSTEM FOR BN-1200 REACTOR

• Jeong-Yong Park
  • Speaker at

    Fabrication Characteristics of Injection-cast Metallic Fuels

• Chang-Gyu PARK
  • Speaker at

    Structural Design and Evaluation of a Steam Generator in PGSFR

• Stefano Passerini
  • Speaker at

    IAEA NAPRO Coordinated Research Project: Physical Properties of Sodium Overview of the Reference Database and Preliminary Analysis Results

• Vladimir Pastukhov
  • Speaker at

    STATISTICAL INVESTIGATION OF RADIATION-INDUCED POROSITY IN BN FUEL CLADDINGS USING SCANNING ELECTRON MICROSCOPY

• Frédéric Payot
  • Speaker at

    The SAIGA experimental program to support the ASTRID Core Assessment in Severe Accident Conditions

• Sandro Pelloni
  • Speaker at

    Low-void-effect sodium-cooled core: Uncertainty of local sodium void reactivity as a result of nuclear data uncertainties

• Claubia Pereira
  • Speaker at

    Neutronic evaluation of a GFR of 100 MWt with reprocessed fuel and thorium using SCALE 6.0 and MCNPX

• Vyacheslav Pershukov
  • Speaker at

    Closing Remarks by Conference General Chair

  • Speaker at

    Welcome Note by Conference General Chair

  • Speaker at

    International research center based on MBIR reactor – cornerstone for Generation 4 technologies development

  • Speaker at

    Topical issues of training of specialists for fast nuclear power engineering and the closed nuclear fuel cycle

• Igor Peshkichev
  • Speaker at

    Mathematical modeling of the mononitride nuclear fuel production processes

• Igor Petrov
  • Speaker at

    Manufacture, Installation and Adjustment of the BN-800 Reactor Plant Equipment

  • Speaker at

    Russian Companies’ involvement in CEFR RP (China) construction

• Eirik Eide Pettersen
  • Speaker at

    Developing an open-source multi-physics tool for simulating advanced nuclear reactors

  • Speaker at

    Simulating circulating-fuel fast reactors with the coupled TRACE-PARCS code

• Jon Phillips
  • Speaker at

    INPRO: Fast Reactors and Enhanced Nuclear Energy Sustainability

• Sylvestre Pivet
  • Speaker at

    Status of the French Fast Reactor Programme

• david plancq
  • Speaker at

    ASTRID French SFR: Progress in Sodium Gas Heat Exchanger development

  • Speaker at

    Progress in the ASTRID Gas Power Conversion System development

• Christophe POINSSOT
  • Speaker at

    1992-2017: 25 years of success story for the Development of Minor Actinides Partitioning Processes

  • Speaker at

    Assessment of the anticipated improvement of the environmental footprint of future nuclear energy systems

• Sergey Porollo
  • Speaker at

    Analysis of experimental data on fission gas release and swelling in mononitride fuel irradiated in BR-10 reactor

• Irina Portnykh
  • Speaker at

    Investigation of Radiation-Induced Swelling of EK-164 Steel, an Advanced Material for BN-600 and BN-800 Claddings

• Alexei Potapov
  • Speaker at

    Pyrochemical recycling of the nitride SNF of fast neutron reactors in molten salts as a part of the short-circuited nuclear fuel cycle

• Sandra POUMEROULY
  • Speaker at

    Impact of the irradiation of an ASTRID-type core during an ULOF with SIMMER-III

• Federico Puente Espel
  • Speaker at

    Participation of Mexico in the OECD/NEA SFR Benchmark using the Monte Carlo code Serpent

• P. Puthiyavinayagam
  • Speaker at

    Development of Smart Component Based Framework for Dynamic Reliability Analysis of Nuclear Safety Systems

  • Speaker at

    Development of Ultra Sub-size Tensile Specimen for Evaluation of Tensile Properties of Irradiated Materials

  • Speaker at

    Advanced Design Features of MOX Fuelled Future Indian SFRs

  • Speaker at

    Design of Sleeve Valve mechanism for Primary Sodium Pump of future FBR

  • Speaker at

    DESIGN VALIDATION OF PFBR FUEL SUBASSEMBLY TRANSPORTATION CASK WITH MOCKUP TRIAL RUN

• Pengrui Qiao
  • Speaker at

    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

• Staffan Qvist
  • Speaker at

    Autonomous Reactivity Control

  • Speaker at

    Passive Shutdown Systems for Liquid Metal-Cooled Fast Reactors

  • Speaker at

    Small fast reactors for arctic regions

• Vincent Reynaud
  • Speaker at

    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

• NATHALIE REYNIER TRONCHE
  • Speaker at

    A comprehensive study of the dissolution of spent SFR MOX fuel in boiling nitric acid (the PHENIX NESTOR-3 case)

  • Speaker at

    First assessment of a digestion method applied to recover plutonium from refractory residues after dissolving spent SFR MOX fuel in nitric acid

• G. Rimpault
  • Speaker at

    Evaluation of βeff measurements from BERENICE programme with TRIPOLI4® and uncertainties quantification

  • Speaker at

    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)

  • Speaker at

    The APOLLO3 scientific tool for SFR neutronic characterization: current achievements and perspectives

• Andrei Rineiski
  • Speaker at

    Fast reactor systems in the German P&T and related studies

• Elena Rodina
  • Speaker at

    Fundamental Approaches to High-power Fast Reactor Core Development

• Gilles RODRIGUEZ
  • Speaker at

    Study of isolation valve for Sodium Fast Reactor

• Sergey Rogozhkin
  • Speaker at

    V&V STATUS OF CFD CODES APPLIED TO BN REACTORS

• FABIEN ROUILLARD
  • Speaker at

    EVALUATION OF COBALT FREE COATINGS AS HARDFACING MATERIAL CANDIDATES IN SODIUM FAST REACTOR

• Evgeny Rozhikhin (IPPE)
  • Speaker at

    Overview of Experiments for Physics of Fast Reactors from the International Handbooks of Evaluated Criticality Safety Benchmark Experiments and Evaluated Reactor Physics Benchmark Experiments

• Nikita Rtishchev
  • Speaker at

    Final Results and Lessons Learned from EBR-II SHRT-17 Benchmark Simulations

  • Speaker at

    SOCRAT-BN integral code for safety analysis of NPP with sodium cooled fast reactors: development and plant applications

• Sergey Rukhlin
  • Speaker at

    Development of the built-in primary sodium purification system for the

• VALENTIN RYCHKOV
  • Speaker at

    Dynamic probabilistic risk assessment at a design stage for a sodium fast reactor.

• ARAVINDAN S
  • Speaker at

    Development of Reverse Flow Blockage Device for Primary Sodium Pumps of Fast Breeder Reactor

• Roman Sadovnichiy
  • Speaker at

    Sensors of content of oxygen dissolved in heavy liquid metal coolants

• Yutaka Sagayama
  • Speaker at

    Current status and future view of the fast reactor cycle technology development in Japan

• Alexander Salyulev
  • Speaker at

    ELECTRICAL CONDUCTIVITY OF MOLTEN LiCl-KCl EUTECTIC WITH COMPONENTS OF SPENT NUCLEAR FUEL

• Oleg Saraev
  • Speaker at

    Closing Up Nuclear Fuel Cycle In a Two-Component System with Thermal And Fast Neutron Reactors

• Massimo Sarotto
  • Speaker at

    Impact of an accidental control rod withdrawal on the ALFRED core: tridimensional neutronic and thermal-hydraulic analyses

• Toshinobu Sasa
  • Speaker at

    Study for Accelerator-driven System in J-PARC/JAEA

• anne saturnin
  • Speaker at

    Evolution of the collective radiation dose from the nuclear reactors through the 2nd to the 4th generation.

• Aleksei Sedov
  • Speaker at

    A Concept of VVER-SCP reactor with fast neutron spectrum and self-provision by secondary fuel

• Aleksei Sedov
  • Speaker at

    "Peculiarities of behavior of Coated Particle fuel in the core of Fast Gas Reactor BGR-1000"

• Yoshihiro Sekio
  • Speaker at

    Evaluation of irradiation-induced point defects migration during neutron irradiation in modified 316 stainless steel

• Evgeny Seleznev
  • Speaker at

    Using of computer code GEFEST800 at the initial stage of NPP operation with BN-800

• Perumal Selvaraj
  • Speaker at

    Sodium testing of fast reactor components

• Alexandr Semchenkov
  • Speaker at

    THE STUDY OF THERMAL-HYDRAULIC PROCESSES IN THE STEAM GENERATOR OF THE BREST-OD-300 REACTOR FACILITY

• Sonat Sen
  • Speaker at

    A Versatile Coupled Test Reactor Concept

• Konstantin Sergeenko
  • Speaker at

    LES-SIMULATION OF HEAT TRANSFER IN A TURBULENT PIPE

• Frédéric SERRE
  • Speaker at

    PLINIUS-2: a new corium facility and programs to support the safety demonstration of the ASTRID mitigation provisions under Severe Accident Conditions

• David Settimo
  • Speaker at

    Superphenix dismantling - Status and lessons learned

• Andrei Shadrin
  • Speaker at

    Reprocessing of fast reactors mixed U-Pu used nuclear fuel: studies and industrial test

  • Speaker at

    Hot test of technique separation of americium and curium

• Maria Shekhanova
  • Speaker at

    Optimization problem for characteristics of fast reactors operating in a closed fuel cycle

• Sergey Shepelev
  • Speaker at

    Development of the new generation power unit with the BN-1200 reactor

• Mikhail Shikhalev
  • Speaker at

    Preliminary Inspection of Spent Fast Reactor Fuel Claddings

• Yonghoon Shin
  • Speaker at

    Characterization of LBE Non-isothermal Natural Circulation by Experiments with HELIOS Test Loop and Numerical Analyses

• Vadim Alexandrovich Shurupov
  • Speaker at

    APPLICATION OF PHYSICAL MODELING WHEN CALIBRATING HIGH RANGE ELECTROMAGNETIC FLOWMETERS

• Kirill Shutko
  • Speaker at

    Corrosion behavior of tube steel for BREST-OD-300 steam generator

  • Speaker at

    Development of steam-water cycle chemistry for steam generator of research reactor MBIR

• IURII SHVETSOV
  • Speaker at

    Decay-heat removal in accidents in fast reactors with liquid metal coolant

• Victoria Shvetsova
  • Speaker at

    Synergetic mechanism of high temperature radiation embrittlement of austenitic steels under long term neutron irradiation at high temperatures

• James Sienicki
  • Speaker at

    Advanced Energy Conversion for Sodium-Cooled Fast Reactors

• S Sikorin (The Joint Institute for Power and Nuclear Research SOSNY of the National Academy of Sciences of Belarus)
  • Speaker at

    A High Density Uranium Zirconium Carbonitride LEU Fuel for Application in Fast Reactors

• Svyatoslav Sikorin
  • Speaker at

    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

• Vladislav Sizarev
  • Speaker at

    On the rational design of fuel assemblies for reactor facilities from the standpoint of providing vibration strength

• Valeri Smolenski
  • Speaker at

    Thermodynamics and separation factor of lanthanides and actinides in system “liquid metal-molten salt”

• Tanju Sofu
  • Speaker at

    Development of Safety, Irradiation, and Reliability Databases based on Past U.S. SFR Testing and Operational Experiences

  • Speaker at

    USDOE NEAMS Program and SHARP Multi-Physics ToolKit for High-Fidelity SFR Core Design and Analysis

• Aleksandr Sorokin
  • Speaker at

    Heat transfer and temperature non-uniformities in pin bundles with heavy liquid metal coolant at various spacing ways

  • Speaker at

    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

• Alexander Sorokin
  • Speaker at

    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

• CLEMENT RAVI CHANDAR SOWRINATHAN
  • Speaker at

    EFFECT OF INLET TEMPERATURE AND OPERATING LINEAR HEAT RATING (LHR) ON THE MAXIMUM ACHIEVABLE BURNUP OF MK-1 CARBIDE FUEL IN FBTR

• CLEMENT RAVI CHANDAR SOWRINATHAN
  • Speaker at

    Performance evaluation of ferroboron shielding material after irradiation in FBTR

  • Speaker at

    Design Safety Limits for Transients in a Metal Fuelled Reactor

• Balija Sreenivasulu (IGCAR)
  • Speaker at

    ADVANCED FLOW-SHEET FOR PARTITIONING OF TRIVALENT ACTINIDES FROM FAST REACTOR HIGH ACTIVE WASTE

  • Speaker at

    FACILITY FOR ADVANCED FUELS THROUGH THE SOL-GEL METHOD

  • Speaker at

    PERFORMANCE EVALUATION OF TIN OXIDE BASED SENSOR FOR MONIOTORING TRACE LEVELS OF H2 IN ARGON COVER GAS PLENUM OF FBTR

  • Speaker at

    Development of Tri-iso-Amyl Phospahte (TiAP) based solvent extraction process as an alternate method for the processing of metallic alloy fuels (U-Pu-Zr and UZr)

• Sergey Starikov
  • Speaker at

    Multiscale computer modeling of nuclear fuel properties at radiation and thermal impacts

• Nicolas Stauff
  • Speaker at

    Evaluation of the OECD/NEA/SFR-UAM Neutronics Reactivity Feedback and Uncertainty Benchmarks

  • Speaker at

    Tradeoff Study of Advanced Transmutation Fuels in Sodium-cooled Fast Reactors

• Andrei Stremin
  • Speaker at

    DETERMINISTIC SAFETY ANALYSIS OF REACTOR BREST-OD-300

• Valery Strizhov
  • Speaker at

    Codes of New Generation Developed for Breakthrough Project

• Tyler Sumner
  • Speaker at

    EBR-II SHRT-17 and SHRT-45R Benchmark Analyses

• Raghupathy Sundararajan
  • Speaker at

    COMPONENT HANDLING SYSTEM : PFBR AND BEYOND

  • Speaker at

    Design and Development of Stroke Limiting Device for Control & Safety Rod Drive Mechanisms (CSRDMs) of future FBRs

  • Speaker at

    EXPERIMENTAL SEISMIC QUALIFICATION OF DIVERSE SAFETY ROD AND ITS DRIVE MECHANISM OF PROTOTYPE FAST BREEDER REACTOR

  • Speaker at

    Testing and Qualification of Trailing Cable system for Prototype Fast Breeder Reactor

• Igor Suslov
  • Speaker at

    Assessment of accuracy from the use of point kinetics when analyzing transition processes in high power fast reactor

• Kiichi Suzuki
  • Speaker at

    Experience on MOX fuel fabrication for fast reactor at PFPF

• Takashi Takata
  • Speaker at

    Numerical Investigation of Sodium Spray Combustion Test with SPHINCS code

• Shigeru Takaya
  • Speaker at

    Proposal of Basic Principles of Maintenance Management for Prototype Reactors

• Lizhen Tan
  • Speaker at

    Creep resistance and fracture toughness of recently-developed optimized Grade 92 and its weldments for advanced fast reactors

• Mariano Tarantino
  • Speaker at

    CIRCE-ICE EXPERIMENTAL ACTIVITY IN SUPPORT OF LMFR DESIGN

• Boris Tarasov
  • Speaker at

    Metal fuel for fast reactors, a new concept

• Maria Tarasova
  • Speaker at

    The way of nitride fuel producing by high voltage electrodischarge compaction

• Sergei Terentev
  • Speaker at

    Full-fledged affination extractive-crystallizng platform for technology validation of the fast reactor spent fuel reprocessing on fast neutrons – the results of first experiments

• Mikhail Ternovykh
  • Speaker at

    System of coordinated calculation benchmarks for a fast reactor with sodium coolant in closed fuel cycle

• Zhao-Fei TIAN
  • Speaker at

    Modelling and Simulation of Heat Transport System and Steam Power Transition System of CEFR

• Georgy Tikhomirov
  • Speaker at

    Topical issues of training of specialists for fast nuclear power engineering and the closed nuclear fuel cycle

  • Speaker at

    System of coordinated calculation benchmarks for a fast reactor with sodium coolant in closed fuel cycle

• Liudmila Tkachenko
  • Speaker at

    DYNAMIC TEST OF EXTRACTION PROCESS FOR AMERICIUM PARTITIONING FROM THE PUREX RAFFINATE

• Dmitriy Tolstoukhov
  • Speaker at

    Providing the competitiveness of nuclear energy in the implementation of PRORYV project

• Georgy Toshinsky
  • Speaker at

    SVBR Project: status and possible development

  • Speaker at

    SVBR-100 as a possible option for developing countries, why?

• Aleksandr Trufanov
  • Speaker at

    Experimental investigations of velocity and temperature fields, stratification phenomena in a integral water model of fast reactor in the steady state forced circulation

• Vladimir Tsygvintsev
  • Speaker at

    X-RAY DIFFRACTION STRUCTURAL ANALYSIS OF STRUCTURAL AND FUEL MATERIALS FOR BN-600 REACTOR

• Kamil Tucek
  • Speaker at

    New catalog on (U,Pu)O2 properties for fast reactors and first measurements on irradiated and non-irradiated fuels within the ESNII+ project

  • Speaker at

    Development of Safety Design Criteria for the Lead-cooled Fast Reactor

• Alexey Tutukin
  • Speaker at

    Application of CFD simulation to validate the BREST-OD-300 primary circuit design

• Alexander Tuzov
  • Speaker at

    Development of Research Nuclear Power Facility with MBIR Multi-Purpose Fast Neutron Research Reactor

• Cetin Unal
  • Speaker at

    Modeling of Lanthanide Transport in Metallic Fuels: Recent Progresses

• Partha Sarathy UPPALA
  • Speaker at

    Development and Validation of EBRDYN code by Benchmark Analysis of EBR-II SHRT-17 Test

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    Thermal Hydraulic Investigation of EBR-II Instrumented Subassemblies during SHRT-17 and SHRT-45R Tests

• Vladimir Usanov
  • Speaker at

    Assessment of a nuclear energy system based on the integral indicator of sustainable development

• Rajan Babu V.
  • Speaker at

    Experiences during construction & Commissioning of electrical power Generation and Evacuation systems in PFBR

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    Lessons and strategies from PFBR to Future Fast Breeder Reactors

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    CHALLENGES DURING CONSTRUCTION OF SODIUM PIPING SYSTEMS FOR 500MWe PROTOTYPE FAST BREEDER REACTOR

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    Challenges During Manufacture of Reactor Components of PFBR

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    Testing and Qualification of shielded flasks for handling sodium wetted large sized components of PFBR

• Matthias Vanderhaegen
  • Speaker at

    Fast Reactors - The Belgian Regulatory Approach

• Willem Frederik Geert Van Rooijen
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    Analysis of the EBR-II SHRT-45R neutronics benchmark with ERANOS-2.0

  • Speaker at

    IAEA NEUTRONICS BENCHMARK FOR EBR-II SHRT-45R

• Artem Varivtcev
  • Speaker at

    CALCULATION OF NEUTRONIC PARAMETERS IN SUPPORT OF A BOR-60 EXPERIMENTAL FA WITH MODERATING ELEMENTS

• Eugeny Varseev
  • Speaker at

    Mass Transfer Simulation Model for Justification Sodium Purification System Characteristics

• Alfredo Vasile
  • Speaker at

    RECENT ACTIVITIES OF THE SAFETY AND OPERATION PROJECT OF THE SODIUM-COOLED FAST REACTOR IN THE GENERATION IV INTERNATIONAL FORUM

  • Speaker at

    Thermal-hydraulics and Decay Heat Removal in GFR ALLEGRO

• Stephane Vaudez
  • Speaker at

    Effects of Oxygen Partial Pressure During Sintering at Laboratory and Industrial Scales on FR MOX Fuels

• Emanuel Vázquez
  • Speaker at

    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)

• Christophe VENARD
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    The ASTRID core at the end of the conceptual design phase

• Mikhail Veshchunov
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    IAEA activities in the area of Nuclear Power Reactor Fuel Engineering

• Barbara Vezzoni
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    IAEA NEUTRONICS BENCHMARK FOR EBR-II SHRT-45R

  • Speaker at

    SIMMER ANALYSES OF THE EBR-II SHUTDOWN HEAT REMOVAL TESTS

  • Speaker at

    Quantitative Evaluation of the Post Disassembly Energetics of a Hypothetical Core Disruptive Accident in a Sodium Cooled Fast Reactor

• Vitaliy Vidanov
  • Speaker at

    Hot test of technique separation of americium and curium

• Dominique Villani
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    Study of isolation valve for Sodium Fast Reactor

• ALEKSEY VINOGRADOV
  • Speaker at

    Numerical – experimental research in justification of fire (sodium) safety of sodium cooled fast reactors

• Igor Volkov
  • Speaker at

    The lead-cooled fast reactor transition to equilibrium operating conditions

• Laurent VOLPE
  • Speaker at

    ASTRID - An original and efficient project organization

• Branislav Vrban
  • Speaker at

    Stability Analysis of a Liquid Metal Cooled Fast Reactor

• karl vulliez
  • Speaker at

    Experimental qualification of rotatable plug seals for Sodium Fast Reactor on a large scale test stand

• Janne Wallenius
  • Speaker at

    SEALER: a small lead-cooled reactor for power production in the Canadian Arctic

• FENGLONG WANG
  • Speaker at

    Study on the limits of confinement leakage rates of pool-type sodium-cooled fast reactor

• Jong Hyuck Won
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    Investigation of the homogenization effect in sodium void reactivity in PGSFR

• David Wootan
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    Design and Fabrication of Closed Loop Systems (CLS) for the Fast Flux Test Facility (FFTF)

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    Lessons Learned from Fast Flux Test Facility Experience

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    Passive Safety Testing at the Fast Flux Test Facility Relevant to New LMR Designs

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    The U.S. Knowledge Preservation Program for Fast Flux Test Facility Data

• qingsheng wu
  • Speaker at

    Neutronics Experimental Verification for ADS with China Lead-based Zero Power Reactor

• Christophe Xerri
  • Speaker at

    Report on the Young Generation Event

• Xiuli Xue
  • Speaker at

    Computational Analysis Code Development for Emergency Heat Removal of Pool-style Fast Reactors

• YOSHIKAZU YAMADA
  • Speaker at

    A Conceptual design of engineering-scale plant applied the simplified MA-bearing fuel fabrication process

• Akira Yamaguchi
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    Current Thermal Hydraulic Activities on Sodium-cooled Fast Reactors in Japan

• Hidemasa Yamano
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    Basic Visualization Experiments on Eutectic Reaction of Boron Carbide and Stainless Steel under Sodium-Cooled Fast Reactor Conditions

• Yong YANG
  • Speaker at

    A Preliminary Study of P&T Scenario on a Sustainable Energy System in China

• HUEE-YOUL YE
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    Hydraulic Design and Evaluation of the PHTS Mechanical Pump of PGSFR

• Alexander Yegorov
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    Comparison of Innovative Nuclear Energy Systems Based on Selected Key Indicators and Their Weighing Factors

• Bangyue YIN
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    Fabrication process of NpO2 pellets

• JAEWOON YOO
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    Compliance of Korean SFR Safety Design Approaches with Generation-IV Safety Design Criteria (Korea, R. of)

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    Status of Sodium Cooled Fast Reactor Development Program in Korea

• Kyungho Yoon
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    Mechanical Design Evaluation of Fuel Assembly for PGSFR

• Kazuo YOSHIMURA
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    Evaluation of multiple primary coolant leakages accidents in Monju with consideration of passive safety features

• Hwan Yeal YU
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    Physics Investigation of a Supercritical CO2–cooled Micro-Modular Reactor (MMR) for Autonomous Load-Follow Operation

• Varvara Yufereva (JSC «N.A. Dollezhal Research and Developmant Institute of Power Engineering»)
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    Methodical uncertainty of criticality precise calculations for fast lead reactor

• Liudmila Zabudko
  • Speaker at

    Development of innovative fast reactor nitride fuel in Russian Federation: state-of-art.

• Donghui ZHANG
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    Research, development and deployment of fast reactors and related fuel cycle in China

• Zhigang Zhang
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    Research and Development on Simulator of Fast Reactor in China

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    Research on modeling and simulation of the primary coolant system for China Experimental Fast Reactor

• Zhijian Zhang
  • Speaker at

    Research and Development on Simulator of Fast Reactor in China

• Dalin Zhang
  • Speaker at

    Conclusions of a Benchmark Study on the EBR-II SHRT-45R Experiment

• qiang zhao
  • Speaker at

    the simulation of reactor physics for China Experimental Fast Reactor

• Igor Zhemkov
  • Speaker at

    Potential Capabilities in Transmutation of Minor Actinides of the BOR-60 Reactor and MBIR Reactor under Construction

• tao zhou
  • Speaker at

    CLEAR-S: A Large Pool-type Components and Thermo-hydraulic Integrated Test Facility for China Lead based reactor

• Keyuan Zhou
  • Speaker at

    Primary Analysis on The Nuclear Energy Development Scenario base on the U-Pu Multicycling with PWR, FR and CNFC in China

• Qi Zhou
  • Speaker at

    Preliminary Design of Zero Power Reactor for CEFR MOX Core

• Zhiwei Zhou
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    Computational Analysis Code Development for core and primary system thermal hydraulic design of SFR

• Huanjun Zhu
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    Expriment and Analysis of Flow distribution of MOX Assembly

• A Zhukov
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    Knowledge Transfer to Young Generation and Technical Reconstruction of BFS Complex

• Ivan Zverev
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    CORE CONDITON MONITORING IN ADVANCED COMMERCIAL SODIUM BN-1200