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Technical Session 1.1

• 037 - Status of SFR Development in Korea
  Y. Kim, Korea

• 041 - Enhancement of JSFR Safety Design and Criteria for Gen.IV Reactor
  K. Aoto, Japan

• 050 - Development of physical conceptions of fast reactors
  Y. Khomyakov, Russia

• 055 - Future Advanced Nuclear Systems and Role of MYRRHA as Waste Transmutation R&D Facility
  H. A. Abderrahim, Belgium

• 062 - The French Fast Reactor Program - Innovations in Support to Higher Standards
  F. Gauche, France

• 417 - Lead-alloy cooled fast reactor development plan and R&D status in China
  Y. Wu, China

Technical Session 1.2

• 261 - The ASTRID Project: Status and Future Prospects
  P. Le Coz, France

• 275 - Status of ASTRID architecture and pre-conceptual design
  P. Alphonse, France

• 336 - The European Lead Fast Reactor strategy and the Roadmap for the Demonstrator ALFRED
  A. Alemberti, Italy

• 375 - BN-1200 reactor power unit design development
  S. Shepelev, Russia

• 398 - Advanced Fast Reactor - 100 - Design Overview
  C. Grandy, USA

Technical Session 1.3

• 127 - Status of ASTRID nuclear island pre-conceptual design
  M. Saez, France

• 242 - Status of ASTRID core studies at the end of predesign phase 1
  M. Chenaud, France

• 331 - The Collaborative Project for a European Sodium Fast Reactor
  A. Vasile, France

• 461 - Advanced Structural Mechanics Design of 500 MWe Commercial SFRs
  G. Gagan, India

Technical Session 1.4

• 272 - A core design approach aimed at the sustainability and intrinsic safety of the European Lead-cooled Fast Reactor
  G. Grasso, Italy

• 295 - Core design study of ultra-long cycle fast reactor concept
  D. Lee, Korea, Replublic of

• 299 - Physics Design and Safety Studies of a 320 MWt Experimental Metal FBR
  K. Devan, India

• 310 - Sample of EDF-R&D 2009-2012 core studies on heterogeneous sodium-cooled fast reactors with low sodium void effect
  D. Schmitt, France

• 347 - A New Design Option for Achieving Zero Void Effect in Large SFR Cores
  D. Verrier, France

Technical Session 1.5

• 132 - Gas Cooled Fast Reactors: Recent Advances and Prospects
  C. Poette,France

• 147 - Recommendations for a demonstrator of Molten Salt Fast Reactor
  E. Merle-Lucotte, France

• 294 - Preliminary Conceptual Design for a Multipurpose Experimental Sodium-Cooled Fast reactor
  M. Kim, Korea, Republic of

• 423 - Study on asymmetric parfait cores with low void reactivity and recycled MAs for the fast reactor
  A. Nagata, Japan

• 476 - Characteristics of Modular Fast Reactor SVBR-100 Using Thorium-Uranium (233) Fuel
  O. Komlev, Russian Federation

Technical Session 2.1

• 024 - The Lead Fast Reactor: Demonstrator (ALFRED) and ELFR Design
  A. Alemberti, Italy

• 026 - Development of fast sodium reactor technology in Russia
  B. Vasilyev, Russian Federation

• 029 - Manufacture and Erection of SFR Components: Feedback from PFBR Experience
  P. Chellapandi, India

• 049 - Overview of U.S. Fast Reactor Technology Program
  R. Hill, USA

• 059 - Evaluation of severe external events on JSFR
  H. Hayafune, Japan

Technical Session 2.2

• 106 - Inverted Steam Generators for Sodium Cooled Fast Reactors
  O. Matal, Czech Republic

• 126 - Sodium-water reaction approach and mastering for ASTRID steam generator design
  M. Saez, France

• 262 - ASTRID power conversion system: assessment on steam and gas options
  G. Laffont, France

• 340 - Hydrodynamic stability analysis method of once-through sodiumheated steam generator with double-walled straight tube
  M. Mito, Japan

Technical Session 2.3

• 120 - Synthesis of results obtained on sodium components and technology through the Generation IV International Forum SFR Component Design and Balance-of-Plant Project
  J. Sienicki, USA

• 263 - Large electro-magnetic pump design for application in the ASTRID sodium-cooled fast reactor
  G. Laffont, France

• 324 - Design and Fabrication of Serpentine Tube Type Sodium to air heat Exchangers for PFBR SGDHR Circuits
  A. Pai, India

• 325 - Innovations in Equipment Erection of Prototype Fast Breeder Reactor (PFBR)
  S. Sandhyapogu, India

• 376 - Objectives of experimental validation of mechanical equipment for BN-1200 reactor plant
  A. Timofeev, Russian Federation

Technical Session 2.4

• 337 - ASTRID In Service Inspection and Repair : review of R&D program and associated results
  F. Baque, France

• 163 - The Hydrogen Detection Technique for SG Protection System
  L. Mingyu, China

• 247 - Safeguards in Prototype Fast Breeder Reactor Monju
  E. Umebayashi, Japan

• 317 - Development of Electrochemical Oxygen Sensors for Liquid Sodium
  B.K. Nollet, United States of America

• 326 - Study on High Sensitive FFDL Technique for Monju and next generation SFR Using Laser Resonance Ionization Mass Spectrometry
  T. Aoyama, Japan

Technical Session 2.5

• 119 - Cooperation on impingement wastage experiment of Mod. 9Cr-1Mo steel using SWAT-1R sodium-water reaction test facility
  F. Beauchamp, France

• 196 - Modelling of the chemical behaviour of sodium fire aerosols during atmospheric dispersion
  T. Gilardi, France

• 245 - R&D and Design Studies for the ASTRID Core-Catcher
  F. Serre, France

• 302 - Development of Under-Sodium Inspection Technique using Ultrasonic Waveguide Sensor
  Y. Joo, Korea, Republic of

• 338 - Acoustic Waves: A Route to Enhance Sodium Fast Reactor Safety
  J. Jeannot, France

Technical Session 3.1

• 033 - Modern Approaches to Safety Assurance of Sodium Fast Reactors of a New Generation
  I. Ashurko, Russian Federation

• 035 - Safety Upgradation of PFBR in wake of Fukushima accident - Severe accident management strategies
  P. Kumar, India

• 047 - SFR Safety Consideration in Light of Fukushima Dai-ichi Accident
  A. Yamaguchi, Japan

• 048 - R&D challenges for SFR design and safety analysis – opportunities for international cooperations
  N. Devictor, France

• 174 - Sodium Fast Reactor Safety and Licensing Research Plan
  M. Denman, USA

• 356 - IAEA Safety Standards for Fast Neutron Reactors and High Temperature Gas-cooled Reactors
  P. Chellapandi, IAEA

Technical Session 3.2

• 150 - Safety design approach for JSFR toward the realization of GEN IV Sodium cooled fast reactor
  S. Kubo, Japan

• 171 - Licensing support experience of the BN-600 operation
  N. Khrennikov, Russian Federation

• 267 - Safety orientations during ASTRID conceptual design phase
  P. Lo Pinto, France

• 374 - Analytical and experimental study for validation of the device to confine BN reactor melted fuel
  S. Rogozhkin, Russian Federation

• 382 - SFRs and GEN IV: ASN actions
  C. Giacomazzi-Belot, France

Technical Session 3.3

• 137 - Sodium experiments on natural circulation decay heat removal and 3D simulation of plenum thermal hydraulics
  H. Kamide, Japan

• 243 - Experimental programs and facilities for ASTRID development related to the Severe Accident Issue
  C. Journeau, France

• 259 - Experimental and Numerical Simulations of Sodium Fire Effects in SFR
  P. Durairaj, India

• 318 - Aspects of Safety Analysis for Sodium Cooled Fast Reactor Design and Licensing
  B. Truong, USA

• 433 - Safety Aspects of Thorium Fuel in Sodium-Cooled Fast Reactors
  F. Franceschini, USA

Technical Session 3.4

• 144 - Investigation of the Coupled Reactivity Effects of the Movable Reflector and Safety Control Rods in the GFR
  Š. Čerba, Slovakia

• 194 - SARGEN_IV: Proposal for harmonized European practices for the safety assessment of innovative fast neutrons spectrum reactors considered in Europe
  D. Blanc, France

• 250 - Safety Strategy of JSFR establishing In-Vessel Retention of Core Disruptive Accident
  Y. Tobita, Japan

• 321 - Post-Fukushima lessons and safety orientations for ASTRID
  B. Carluec, France

• 412 - Modelling Validation of Transients and Initial Phase of Accident Scenarios for Sodium Fast Reactors
  S. Perez-Martin, Germany

• 458 - Safety features of a power unit with the BREST-OD-300 reactor
  V. Smirnov, Russian Federation

Technical Session 3.5

• 260 - Safety Analysis Results of Representative DEC Accidental Transients for the ALFRED Reactor
  G. Bandini, Italy

• 297 - LFR safety approach and main ELFR safety analysis results
  E. Bubelis, Germany

• 395 - Principles of Inherent Self-Protection Realized in the Project of Small Sized Modular Reactor SVBR-100
  G. Toshinsky, Russia

• 420 - Preliminary safety analysis of China Lead Alloy Cooled Research Reactor CLEAR-I
  M. Jin, China

• 460 - Severe Accident Scenarios: Indian Perspective
  P. Chellapandi, India

Technical Session 4.1

• 028 - Development of Structural Materials for JSFR - Overview and Current Status
  T. Asayama, Japan

• 032 - Development of Structural Core Components for Breeder Reactors
  N. Saibaba, India

• 039 - Materials Performance in Sodium-Cooled Fast Reactors: Past, Present, and Future
  K. Natesan, USA

• 051 - Achievement and new challenges for high performance materials
  C. Fazio, Germany

• 198 - Materials Options of Steam Generator For Sodium-Cooled Fast Reactor
  X. Fu, China

Technical Session 4.2

• 464 - French R&D on materials for the core components of Sodium Fast Reactors
  M. Le Flem, France

• 190 - Fabrication and characterization of aluminium-containing ferritic ODS alloys for improved corrosion resistance
  J. Hoffmann, Germany

• 240 - Mechanical Properties of Cladding and Wrapper Materials for ASTRID Fast-Reactor Project
  P. Gavoille, France

• 252 - Irradiation Performance of Oxide Dispersion Strengthened (ODS) Ferritic Steel Claddings for Fast Reactor Fuels
  T. Kaito, Japan

• 380 - Optimization of the Fabrication Route of Ferric/Martensitic Oxide Dispersion Strengthened Cladding Tubes: Mettallugical Approach and Pilgering Numerical Modeling
  R. Logé, France

Technical Session 4.3

• 131 - Development of Advanced 9Cr Ferritic-Martensitic Steels and Austenitic Stainless Steels for Sodium-Cooled Faster Reactor
  T. L. Sham, USA

• 230 - Irradiation experiment to determine effect of long-term low dose irradiation on FBTR grid plate material
  R. Divikar, India

• 287 - Experimental and Theoretical Investigations of Ferro Boron as In-vessel Shield Material in FBRs
  K. Ramanathapura Subbaraya, India

• 305 - Fabrication and Evaluation of SFR Cladding Tubes
  S. H. Kim, Korea, Republic of

• 404 - Synthesis of R&D results on 9%Cr steels for Steam Generators of Sodium Fast Reactors
  C. Cabet, France

Technical Session 4.4

• 129 - Corrosion of materials in liquid metals considered as fast reactor coolants
  F. Balbaud-Célérier, France

• 186 - Study on the chemical compatibility of SiC/SiC composites as core materials for Sodium Fast Reactors
  J. Braun, France

• 188 - Mechanical modelling of SiC/SiC composites and design criteria
  F. Bernachy-Barbe, France

• 348 - Development of Welding and Hardfacing Technology: challenges for ASTRID project
  T. Marlaud, France

• 383 - Materials for ALFRED and ELFR – selection and challenges
  A. Weisenburger, Germany

Technical Session 5.1

• 020 - Concept and development status of fast breeder reactor fuels in the FaCT project
  S. Maeda, Japan

• 025 - Development, fabrication and characterization of fuels for Indian fast reactor programme
  A. Kumar, India

• 052 - Status of SFR Metal Fuel Development
  C. B. Lee, Korea, Republic of

• 283 - Outcomes on oxide fuel developments for minor actinides recycling
  F. Delage, France

Technical Session 5.2

• 195 - Minor Actinides Burn-up Enhancement in the European Sodium Fast Reactor Through Moderator Material Addition
  R. Ramos, Argentina

• 282 - Overview of CEA's R&D on GFR fuel element design: from challenges to solutions
  M. Zabiego, France

• 350 - Progress in Understanding of Fuel-Cladding Chemical Interaction in Metal Fuel
  K. Inagaki, Japan

• 366 - New Fuel Alloys Seeking Optimal Solidus and Phase Behaviours for High Burn-up and TRU Burning
  R. Mariani, USA

• 463 - New Concept of Designing Composite Fuel for Fast Reactors with Closing Fuel Cycle
  A. M. Savchenko, Russia

Technical Session 5.3

• 110 - Out-of-pile thermophysical properties of metallic fuel for fast reactors in India
  J. Banerjee, India

• 111 - Fabrication of Metallic Fuel Slugs for Irradiation Experiments in Fast Breeder Test Reactor
  M. T. Saify, India

• 193 - Dilatometric Study of U_1-xAm_xO_2±δ Transmutation Fuels
  F. Lebreton, France

• 227 - Sinterability of ZrN and (Zr_0.6Dy_0.4)N pellets - surrogate fuel fabrication for ELECTRA
  M. Pukari, Sweden

• 253 - Analysis of oxygen potentials in MOX and MA-bearing MOX fuels and application to nuclear fuel technologies
  M. Kato, Japan

Technical Session 5.4

• 229 - Performance assessment of MOX fuel with Alloy D9 cladding and wrapper irradiated in FBTR
  J. Jojo, India

• 306 - Irradiation of SFR metal fuel in HANARO and the results of post irradiation examination
  B. O. Lee, Korea, Republic of

• 392 - Minor Actinide Transmutation Performance in Fast Reactor Metal Fuel
  H. Ohta, Japan

• 402 - Irradiation and Post-irradiation Examination of AFC-1 Transmutation Metallic Fuels for Fast Reactors
  H.J.M. Chichester, USA

• 450 - Summary of the Minor Actinide-bearing MOX AFC-2C and -2D Irradiations
  K. J. McClellan, USA

Technical Session 6.1

• 038 - Industrial maturity of FR fuel cycle processes and technologies
  J. Brueziere, France

• 065 - The United States Department of Energy Fuel Cycle Technologies Program
  M. Regalbuto, USA

• 053 - Safety of Advanced Nuclear Fuel Cycles
  T. Fanghaenel, EC

• 056 - Progress in Pyroprocessing Technology at KAERI
  H. Lee, Korea, Republic of

• 045 - Chemical and technological issues of fast reactors fuel cycle
  A. Shadrin, Russia

Technical Session 6.2

• 113 - Technological developments in safe and efficient fabrication of fast reactor fuel elements
  R. B. Bhatt, India

• 199 - Integrated Recycling Test Fuel Fabrication
  R. Fielding, USA

• 296 - Research and development for the fabrication of minor actinide-bearing fuel materials and technologies
  F. Jorion, France

• 388 - Metallic Fuel Casting Development and Parameter Optimization Simulations
  R. Fielding, USA

Technical Session 6.3

• 273 - Overview of the French R&D program for the development of minor actinides separation processes
  C. Rostaing, France

• 291 - Transmutation scenarios impacts on advanced nuclear cycle (fabrication and reprocessing plants, transportation
  A. Saturnin, France

• 313 - Overview of the Main Achievement of the FP7 EURATOM Collaborative Project ACSEPT
  S. Bourg, France

• 393 - Combined (Pyro+Hydro) technology for FR SNF reprocessing
  A. Shadrin, Russia

Technical Session 6.4

• 212 - Scenarios for Minor Actinides Transmutation in the Frame of the French Act for Waste Management
  M. Tiphine, France

• 169 - Impact of minor actinide transmutation options on geological disposal - The French case
  J. Hoorelbeke, France

• 140 - Transmutation in ASTRID
  J. Grouiller, France

• 220 - The ASGARD project, an introduction
  C. Ekberg, Sweden

• 413 - The Molten Salt Fast Reactor as Highly Efficient Transmutation System
  B. Merk, Germany

Technical Session 6.5

• 219 - Feedback on RNR fuel fabrication at AtPu facility, as a support to the design of a future facility
  T. Geneves, France

• 256 - An Indian perspective of the Development of Fast Reactor Fuel Reprocessing Technology
  A. Ravisankar, India

• 276 - French Experience and R&D Challenges for an Industrial SFR MOX Fuel Treatment
  M. Masson, France

• 293 - Polyvalent fuel treatment facility (TCP): shearing and dissolution of used fuel at La Hague facility
  F. Lelièvre, France

• 444 - Treatment of high-level waste arising from pyro-chemical processes
  A. Lizin, Russia

Technical Session 7.1

• 021 - DOE-CEA benchmark on SFR Astrid innovative core: neutronic and safety transients simulation
  T. Sofu, United States of America

• 043 - Modelling of Multi-Physics Phenomena in Fast Reactors Design/Safety and Experimental Validation
  H. Ninokata, Japan

• 057 - Experimental Studies for Safety Grade Decay Removal System of Prototype Fast Breeder Reactor
  G. Padmakumar, India

• 063 - Developing a Comprehensive Software Suite for Advanced Reactor Performance and Safety Analysis
  D. Pointer, United States of America

• 448 - NEA activities in preserving, evaluating and applying data from fast reactor experiments
  N. Gulliford, OECD-NEA

Technical Session 7.2

• 141 - Evaluation on Calculation Accuracy of the Sodium Void Reactivity for Low Void Effect Fast Reactor Cores with Experimental Analyses
  K. Sugino, Japan

• 142 - Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the MONJU Reactor Vessel
  H. Ohira, Japajn

• 187 - Status and Future Challenges of CFD for Liquid Metal Cooled Reactors
  F. Roelofs, Netherlands

• 197 - APOLLO3® Roadmap : a new generation of simulation tools for the neutronic core calculation of the ASTRID prototype
  B. Roque, France

• 254 - Evaluation of Sodium-cooled Fast Reactor Neutronic Benchmarks
  N. Stauff, USA

Technical Session 7.3

• 288 - DRESDYN - A new platform for liquid thermodraulic studies and measurement technique developments
  G. Gerbeth, Germany

• 314 - Activities on Experimental Substantiation of SFR Safety in Accidents with Sodium Boiling
  I. Ashurko, Russian Federation

• 346 - Benchmark Analyses of the Shutdown Heat Removal Tests Performed in the EBR-II Reactor
  L. Briggs, United States of America

• 363 - STAR-CD / CATHARE coupling methodology for thermalhydraulic calculations on primary loop and heat exchangers in sodium-cooled fast reactor
  B. Farges, France

• 389 - Thermal-Hydraulic Assessment of HLM-cooled pin bundle in CIRCE pool facility
  M. Tarantino, Italy

Technical Session 7.4

• 115 - Fuel Behaviour Simulation Code FEMAXI-FBR Development for SFR Core Disruptive Accident Analysis
  T. Okawa, Japan

• 156 - FAST code system: review of recent applications
  K. Mikityuk, Switzerland

• 241 - Recent modelling improvements in fuel performance code GERMINAL for SFR oxide fuel pins
  M. Lainet, France

• 435 - Current Status of the LIFE Fast Reactors Fuel Performance Codes
  A. M. Yacout, USA

Technical Session 7.5

• 189 - Calculation and Analysis of Neutron Time-spatial Kinetics in Uncontrolled Withdrawal Accident of Regulating Rod in CEFR
  X. Li, China

• 236 - Modelling and Simulation of Operator Training Simulator for Prototype Fast Breeder Reactor
  J. Thangavelu, India

• 244 - Code strategy for simulating Severe Accident Scenario
  C. Suteau, France

• 401 - Sensitivity analyses by Generalized Perturbation Theroy (GPT) methods applied to GUINEVERE and MHYRRA lead fast reactors
  M. Carta, Italy

• 425 - Sensitivity and Uncertainty Analyses for Validation of Neutronics Calculations in Safety Assessment Support at IRSN
  E. Ivanov, France

Technical Session 7.6

• 208 - CEFR irradiation test and application
  X. Chen, China

• 237 - Recent analyses of PHENIX End of Life Tests and perspectives
  B. Fontaine, France

• 426 - Experimental and calculating substantiation of reactivity balance and energy-release distribution in BN-600 core
  A. Moiseev, Russian Federation

• 456 - Experimental Potentialities of MBIR Reactor
  I. Tretiyakov, Russian Federation

• 466 - Effect of Heterogeneity of JSFR Fuel Assemblies to Power Distribution
  T. Takeda, Japan

Technical Session 8.1

• 022 - A global assessment of fast reactors in the future
  J. Devezeaux de Lavergne, France

• 031 - Japanese FR Deployment Scenario Study after the Fukushima Accident
  K. Ono, Japan

• 036 - Economics of fast reactors – an Indian perspective
  T. K. Mitra, India

• 040 - The concept of phased deployment and closure of the nuclear fuel cycle on the basis of fast reactors in the conditions of uncertainty of the scale of the future development of nuclear power
  V. Kagramanyan, Russian Federation

• 069 - Major findings of the INPRO collaborative project on Global Architecture of Innovative Nuclear Energy Systems with Thermal and Fast reactors and a Closed Nuclear Fuel Cycle (GAINS)
  V. Kuznetsov, IAEA

• 436 - Commercial U.S. Vendors Focus on Reducing the Cost of Fast Reactors
  D. Fraser, USA

Technical Session 8.2

• 105 - Fuel cycle studies on Minor Actinide burning in gas cooled fast reactors
  M. Szieberth, Hungary

• 133 - 3 Investment Scenarios for Fast Reactors in Europe
  B. Shoai Tehrani, France

• 152 - Non-Electric Applications of Fast Reactors
  H. Safa, France

• 344 - Analysis of scenarios of the inclusion of fast reactors in the nuclear power of Russia in the context of sustainable development with the use of the INPRO methodology
  V.I. Usanov, Russian Federation

• 358 - Fast reactors as a solution for future small-scale nuclear energy
  A. Kudryavtseva, Russian Federation

Technical Session 8.3

• 211 - Scenarios for Fast Reactor Deployment with Plutonium Recycling
  C. Coquelet-Pascal, France

• 233 - Fast Reactor Systems and Innovative Fuels for Minor Actinides Homogeneous Recycling
  R. Calabrese, Italy

• 292 - EDF research scenarios for closing the Plutonium cycle
  J. Le Mer, France

• 332 - Fast reactors and nuclear non-proliferation
  A. Chebeskov, Russian Federation

• 379 - Options for UK plutonium in SFR fuel cycles
  M. Gill, United Kingdom

Technical Session 9.1

• 023 - Prototype and Industrial SFRs: Yesterday, Today, Tomorrow
  J. Sauvage, France

• 030 - Recent Progress and Status of Monju
  S. Kondo, Japan

• 054 - International Experience with Fast Reactor Operation and Maintenance
  J. Sackett, USA

• 060 - Operating experience from the BN600 sodium-cooled fast reactor
  O. Potapov, Russia

• 067 - Twenty six years of operating experience of FBTR and Feedback to Future Reactor Design
  B. Anandapadmanaban, India

• 459 - Experience and solutions on the decommissioning of sodium-cooled fast reactors
  L. A. Kochetkov, Russia

Technical Session 9.2

• 103 - Restoration work for obstacle and upper core structure in reactor vessel of experimental fast reactor "Joyo" (2)
  M. Takamatsu, Japan

• 151 - Evaluation on Coolability of the Reactor Core in Monju by natural circulation under Earthquake and subsequent Tsunami event
  F. Yamada, Japan

• 177 - Phenix: a reprocessing and multiple recycling experiment, unique in the world
  J. Guidez, France

• 377 - Validation of BN reactor plant long-term operation
  O. Vilensky, Russia

• 442 - Dismantling of large components from the PHENIX reactor
  A. Roux, France

Technical Session 10.1

• 034 - Education & Training in support to Sodium Fast Reactors around the world
  C. Latge, France

• 044 - Overview of U.S. Knowledge Management Program for Fast Flux Test Facility Data
  R. Omberg, USA

• 061 - Overview of U.S. Knowledge Management Program for Fast Flux Test Facility Data
  S. Srinivasula, India

• 066 - A new impetus for E&T on Fast neutrons reactors in Europe: incentives, status, perspectives
  C. Renault, France

• 422 - Information Sharing Framework among Experts for Facilitating Development of Fast Reactors and Fuel Cycles
  Y. Kawakubo, Japan

• 441 - IAEA Activities in the Area of Fast Reactors and Related Fuels and Fuel Cycles
  S. Monti, IAEA

Technical Session 10.2

• 149 - ELECTRA-FCC: A Swedish R&D centre for Generation IV systems
  J. Wallenius, Sweden

• 316 - Knowledge passing on in France in the perspective of ASTRID realization
  C. Latge, France

• 405 - Fast Reactor Knowledge Organization System: live demonstration
  A. Pryakhin, IAEA

• 406 - Fast Reactor Knowledge Preservation: Implementation and Challenges
  A. Pryakhin, IAEA

• 429 - The ENEN-III Project: Technical Training on the Concepts and Design of GEN IV Nuclear Reactors
  T. Berkvens, Belgium