Name: International Conference on Fast Reactors and Related Fuel Cycles FR22: Sustainable Clean Energy for the Future (CN-291)
Start: 2022-04-19T08:00:00+02:00
End: 2022-04-22T18:30:00+02:00
Location: Vienna, Austria

International Conference on Fast Reactors and Related Fuel Cycles FR22: Sustainable Clean Energy for the Future (CN-291)

from Tuesday, 19 April 2022 (08:00) to Friday, 22 April 2022 (18:30)

Monday, 18 April 2022
Tuesday, 19 April 2022
09:30
09:30 - 10:20
Contributions

09:30 IAEA Opening Address - Rafael Grossi

09:40 Conference Chair Address - Arun Kumar Bhaduri

09:50 Administrative Remarks - Amparo Gonzalez-Espartero (Scientific Secretary)
10:20

10:20 - 10:30
10:30
10:30 - 12:00
Contributions

10:30 China Key Note - Hongyi Yang

10:42 France Key Note - Frederic Serre

10:54 India Key Note - Balasubramaniam Venkataraman

11:06 Japan Key Note - Hideki Kamide

11:18 Republic of Korea Key Note - Lim Chae Young

11:30 Russian Federation Key Note - Vyacheslav Pershukov

11:42 United States Key Note - Alice Caponiti
12:00

12:00 - 13:00
13:00
13:00 - 15:00
Contributions

13:00 DEVELOPMENT OF BN REACTOR TECHNOLOGY IN RUSSIA - Sergey Shepelev (JSC «Afrikantov OKBM»)

13:12 Progress in the Design and R&D for future FBRs - RAGHUPATHY S. (Indira Gandhi Centre for Atomic Research, Kalpakkam)

13:24 Overview of U.S. Fast Reactor Technology R&D Program - Robert Hill (Argonne National Laboratory)

13:36 Progress in conceptual design of a pool-type sodium-cooled fast reactor in Japan - Atsushi Kato (JAEA)

13:48 Status of Generation-IV Lead Fast Reactor Activities - Alessandro Alemberti (Ansaldo Nucleare)

14:00 The Status of the ALFRED Project - Marco Caramello (Ansaldo Nucleare)

14:12 MYRRHA, the Belgian prototype that fascinates the world - Didier De Bruyn (SCK CEN)

14:24 GFR Research and Development Programme in V4 countries - Petr Vácha (UJV Řež, a.s.)
13:00 - 15:00
Contributions

13:00 Creep and Tensile Properties of Indian Advanced Fast Reactor Clad tubes (IFAC-1) for Future FBRs - Prasad Reddy G. V. (Head, Creep Studies Section & Assistant Prof., HBNI )

13:12 Thermally conductive liquid-metal sublayer in fuel element - Michael Orlov (Private institution «Innovation and technology center for the «PRORYV» project»)

13:24 FABRICATION AND PERFORMANCE ASSESMENT OF ODS FECRAL CLADDING TUBE - Shi Liu (Institute of Metal Research, China Academy of Sciences)

13:36 Gear Test Assembly: First Liquid Metal Component Testing in METL - Edward Kent (Argonne National Laboratory)

13:48 Influence of Low Dose Irradiation on Permanent Core Structural Materials of PFBR - Ran Vijay Kumar (Indira Gandhi Centre for Atomic Research)

14:00 Sodium coolant: interaction with its environment and coolant processing - Christian LATGE (CEA )

14:12 Investigation of sodium purification - Viktor Alekseev (SSC IPPE)

14:24 Development and Demonstration of Diffusion-type Hydrogen Meters for Sodium-cooled Fast Reactors - Hual-Te Chien (Argonne National Laboratory)
Poster Session
Poster Session
13:00 - 17:40
Contributions

13:00 DESIGN & DEVELOPMENT OF CUSTOM SHAPED BACK-UP SEAL IN SILICONE FOR PFBR - Sriramachandra Aithal (Indira Gandhi Centre for Atomic Research, Kalpakkam)

13:00 LARGE-SCALE HYDROGEN PRODUCTION; Fast-neutron Reactors Coupled to Thermochemical Copper-Chlorine Hydrogen Plant - Rami El-Emam (Ontario Tech University)

13:00 CFD ANALYSES OF THE ALFRED HOT PLENUM - Dirk Visser (NRG)

13:00 INDUSTRIAL ENERGY COMPLEX WITH FAST NEUTRON REACTOR - Andrey Petrenko

13:00 New Finite Element Neutron Kinetics Code System FENNECS/ATHLET for Coupled Safety Assessment of (Very) Small and Micro Reactors - Jeremy Bousquet (GRS gGmbH)

13:00 Investigation of characteristics of fast power reactor with an additional function of large-scale production of plutonium-238 - Evgeny Kulikov (National Research Nuclear University MEPhI)

13:00 The neutronic study of the nitride fuel loaded CiADS core - Youpeng Zhang (Fudan University)

13:00 On substantial slowing down of the kinetics of fast transient processes in fast reactor - Evgeny Kulikov (National Research Nuclear University MEPhI)

13:00 Simple Design Comparison of uranium nitride pin cell assembly and matrix fuel assembly for a Lithium Cooled Fast Reactor - Raul Pineda (IAEA FELLOW)

13:00 Development of Burnup Analysis System for rotational and Spiral Fuel Shuffling scheme in Breed-and-Burn Fast Rectors - Khanh Hoang Van (aInstitute for Nuclear Science and Technology, Vietnam Atomic Energy Institute)

13:00 Hybrid high power fast breeder reactor with metallic fuel and additives consisting with lightweight atoms - IURII Drobyshev (Russian Federation)

13:00 Leak-Before-Break Design of Double-Walled Once-Through Steam Generators for Lead Cooled Fast Reactor - Taeyong Kim (UNIST)

13:00 The "ALFRED White Book": a business card of the project - Francesco Lodi (ENEA) Giacomo Grasso (Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA)) Gabriele Firpo (Ansaldo Nucleare SpA) Daniela Diaconu (RATEN/ICN)

15:10 Two-Component Energy Industry under Conditions of Closed Nuclear Fuel Cycle: Economic Benefits - Mariia Roslaya

15:10 A Study on the Development of a Procedure Complexity Evaluation and Optimization for Operating Procedures of China Experimental Fast Reactor - Qi Zhou

15:10 Development of a 15 kg servo manipulator for remote handling applications - Jagadishan D (IGCAR)

15:10 NEXT GENERATION NUCLEAR POWER: RADIOLOGICAL SUSTAINABILITY AND ECOLOGICAL ADVANTAGES - Viktor Ivanov

15:10 INTEGRATED RADIATION AND HYGIENIC APPROACH TO PRODUCTION SAFETY. ASSESSMENT OF THE IMPACT ON PUBLIC HEALTH - Evgeny Metlyaev (State Research Center – Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency)

15:10 CORROSION HYDROGEN MASS TRANSFER IN FAST REACTOR STEAM GENERATORS OF THE SODIUM-WATER TYPE - Vladimir Smykov (SSC IPPE, JSC)

15:10 Novel Electrical, Electronics and Instrumentation systems for Fast Reactor Fuel Reprocessing Plants - Prakash Bhanu Mathews Geo

15:10 Design of experimental scheme for activation method of China demonstration fast reactor - XIAO HU (China Institute of Atomic Energy)

15:10 Nuclear Hydrogen and Fast Reactors - Ioan Iordache (ICSI Rm. Valcea)

15:10 Numerical Investigation of Cellular Convection in the Cover Gas space of Fast Breeder Test Reactor - Kanha Chaturvedi (Dept. of Atomic Energy, IGCAR)

15:10 ULTRASONOSCOPY SYSTEM “VIZUS” FOR SODIUM-COOLED BN-TYPE REACTORS - Dmitrii Lesiukov (JSC “Afrikantov OKBM”)

15:10 EXPORT OF RBN WITH SNCD AND NUCLEAR PROLIFERATION RISKS - Vladimir Kuchinov

15:10 RISK FACTORS OF COMPLEX RADIATION AND NON-RADIATION EFFECTS ON THE HEALTH OF PERSONNEL IN ASSESSING THE IMPACT OF THE PRODUCTION OF INNOVATIVE FUEL FOR FAST REACTORS - Oleg Parinov (Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency) Alexander Samoilov (Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency)

15:10 Sustainability of nuclear and non-nuclear power generation options under Russian conditions: a comparative evaluation study - Stepan Kviatkovskii (SC Rosatom)

15:10 New Concepts and Methodologies for the Effective Deployment of Gen IV reactors - BOMA WILCOX (Nigeria Atomic Energy Commission)
13:00 - 15:00
Contributions

13:00 Neutronics Benchmark of CEFR Start-Up Tests: An IAEA coordinated research project - Nikoleta MORELOVA (IAEA)

13:12 CEFR Physical Start-Up Tests: the Core Specifications and Experiments - Xingkai Huo

13:24 Verification and validation of neutronic codes using the start-up fuel load and criticality tests performed in the China Experimental Fast Reactor - Armando Miguel Gomez Torres (Instituto Nacional de Investigaciones Nucleares)

13:36 Neutronics Benchmark of CEFR Start-Up Tests: Temperature Coefficient, Sodium Void Worth, and Swap Reactivity - Jiwon Choe (Ulsan National Institute of Science and Technology )

13:48 Neutronics Benchmark of CEFR Start-Up Tests: Reaction Rates and Reactivity Coefficients - Taek Kyum Kim (Argonne National Laboratory)

14:00 BLIND PHASE RESULTS FOR TRANSIENT SIMULATIONS OF THE FFTF LOSS OF FLOW WITHOUT SCRAM TEST #13 - Anton Moisseytsev (Argonne National Laboratory)

14:12 Blind-Phase Results of the FFTF Neutronic Benchmark - Nicolas Stauff (Argonne National Laboratory)
15:00

15:00 - 15:10
15:10
15:10 - 17:40
Contributions

15:10 Basis for the Safety Approach (BSA) for Design & Assessment of Generation IV Nuclear Systems - Paul Gauthé (CEA)

15:22 EXAMPLES OF AREAS OF NOVELTY IN LIQUID METAL FAST REACTORS TO CONSIDER IN THE REVIEW OF APPLICABILITY OF THE IAEA SAFETY STANDARDS: FISSION PRODUCT RETENTION BARRIERS: DIFFERENCES BETWEEN LIQUID METAL FAST REACTORS AND LIGHT WATER REACTORS - Paula CALLE VIVES (IAEA)

15:34 System Safety Assessment of the Generation IV Lead Fast Reactor - Kamil Tucek (European Commission, Joint Research Centre)

15:46 France-Japan Collaboration on the SFR Severe Accident Studies: Outcomes and future work program - SHIGENOBU KUBO (JAEA)

15:58 Safety Analysis of the ARC-100 Sodium-Cooled Fast Reactor - Tyler Sumner (Argonne National Laboratory)

16:10 Approach for ALFRED licensing in Romania - Giacomo Grasso (Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA))

16:22 Activities of the GIF Safety and Operation Project of Sodium-Cooled Fast Reactor Systems - Hidemasa Yamano (Japan Atomic Energy Agency)

16:34 Application of the practical elimination concept within the framework of the ESFR-SMART project to improve the intrinsic safety of the sodium-cooled fast reactor - Joel Guidez (CEA)

16:46 Application of a Risk-Informed Performance-Based Approach for the Authorization of the Versatile Test Reactor - Jason Andrus (Idaho National Laboratory)
15:10 - 17:40
Contributions

15:10 Modeling the optimal economic structure of a global deploying nuclear power system with fast and thermal reactors in a partially closed nuclear fuel cycle - Alexander Yegorov (IPPE)

15:22 KEY ASPECTS OF COMPETITIVENESS FOR INDUSTRIAL ENERGY COMPLEX WITH FR AND CLOSED NFC - Dmitriy Tolstoukhov

15:34 TECHNICAL AND ECONOMICAL FEATURES OF COMMERCIAL SODIUM FAST REACTOR IN FRANCE - DAVID SETTIMO (EDF)

15:46 SPECIFIC FEATURES OF THE EXPORT OF RUSSIAN TECHNOLOGIES OF FAST REACTORS AND A CLOSED NUCLEAR FUEL CYCLE - Aleksandr CHEBESKOV (IPPE)

15:58 Development status of commercial SMRs and its experience to China - Ping Li (China Institute of Atomic Energy)

16:10 Effect of Reactor Technology on Economics of SMR Projects - Ilya Zhuravlev

16:22 Comparative multi-criteria analysis of scenarios of the Russian nuclear energy development in the context of uncertainty knowledge about the future - Alexander Yegorov (IPPE)

16:34 EFFECTIVE FUEL SUPPLY OF TWO-COMPONENT NUCLEAR ENERGY SYSTEM WITH VVER-BN REACTORS - Elena Marova (JSC “Afrikantov OKBM”)

16:46 Export Potential and Commercialization Conditions of Fast Reactors Considering Non-Proliferation Items - Nadezhda Salnikova (JSC "Afrikantov OKBM")

16:58 TECHNOLOGICAL SUPPORT OF THE NON-PROLIFERATION FOR SVBR-100 FUEL CYCLES - Oleg Komlev (JSC “AKME-engineering”)

17:10 The INPRO project studies on the double-component nuclear power systems with the closed fuel cycle and fast reactors: past and future - Alexander BYCHKOV (Senior Nuclear Engineering Expert - INPRO)
15:10 - 17:40
Contributions

15:10 Reactor Core Viewing System for the pre-commissioning stage inspection of reactor core components of Prototype Fast Breeder Reactor - Chellapandian Ramalingam (Reactor Design and Technology Group, Indira Gandhi Centre for Atomic Research)

15:22 Experience in Preheating of PFBR Reactor Assembly - A JYOTHISHKUMAR (D A E)

15:34 Commissioning and Operating Experience for Secondary Sodium Systems and is Auxiliaries of PFBR - NISHANTH SAHU (DAE)

15:46 Advanced in-situ Calibration and Probe Release Mechanism for PFBR SG Inspection System (PSGIS) - Joel Jose

15:58 Treatment of sodium of Superphenix Fast Breeder Reactor - Dominique VILLANI (Framatome)

16:10 Operating Experience of FBTR - THANGAMANI M (IGCAR,INDIA)

16:22 Fuel handling Experience of FBTR - MURALITHARAN G (IGCAR / DAE / KALPAKKAM)

16:34 EXPERIENCE OF OPERATIONAL CHEMICAL CLEANING OF BN-600 STEAM GENERATOR EVAPORATORS FROM CORROSION PRODUCT DEPOSITS - Kristina Legkikh

16:46 Design, Experimental trials and Qualification of explosive welding technique for plugging of degraded PFBR Steam Generator tubes - Visweswaran Padmanabhan (Reactor Design and Technology Group, Indira Gendhi Centre for Atomic Research)

16:58 BOR-60 REACTOR OPERATING EXPERIENCE, WORK ON IMPROVING SAFETY AND EXTENDING LIFETIME - Alexey Izhutov (JSC SSC RIAR)

17:10 PROBLEMS OF DECOMISSIONING FAST REACTORS AND WAYS OF THEIR SOLUTION ON THE BASIS OF THE BR-10 RESEARCH REACTOR - Vladimir Smykov (SSC IPPE,JSC)
Wednesday, 20 April 2022
09:30
09:30 - 10:33
Contributions

09:30 European Commission (EC) Key Note - Maria Betti (TBV)

09:42 Generation IV International Forum Key Note - Bob Hill

09:54 OECD/Nuclear Energy Agency Key Note - Tatiana Ivanova

10:06 International Atomic Energy Agency (IAEA) Key Note - Aline Des Cloizeaux

10:18 YGE Winner: Advanced Functional Materials for Next-Generation Fuel Reprocessing - Kuntal Kumar Pal

10:23 YGE Winner: Production of Mo-99 isotope in the BN reactor by beryllium blocks - Oksana Kucheryavykh

10:28 YGE Winner: Small Modular Fast Reactors for the ASEAN Region: Implementation of the TRISO Fuel Particle Concept as a Regional Variant of the Fast Reactor - Tan Zhe Chuan
10:33

10:33 - 10:40
10:35 Poster Session
Poster Session
10:35 - 17:00
Contributions

10:40 DEVELOPMENT OF SUBMERGED ELECTROMAGNETIC PUMP FOR LIQUID LEAD - Denis Obukhov (Joint Stock Company “D.V. Efremov Institute of Electrophysical Apparatus” (JSC «NIIEFA»))

10:40 The working capacity analysis of boron carbide after two-year operation as an emergency protection material of the fast reactor - Evgenii Kinev (JSC «INM»)

10:40 Impact of Core Materials on The Fuel cladding Irradiation Damage in Breed-and-Burn Fast Reactors - Odmaa Sambuu (School of Engineering and Applied Sciences, National University of Mongolia)

10:40 Experimental study on sodium insulation interaction and its effect on structural material - Avinash Ch SSS (Indira Gandhi Center for Atomic Research)

10:40 CURRENT STATE AND ISSUES OF THE HEAVY LIQUID METAL COOLANT TECHNOLOGY DEVELOPMENT (PB, PB-BI) - Radomir Askhadullin (Institute of Physics and Power Engineering, Join-Stock Company (IPPE JSC))

10:40 NON-DESTRUCTIVE METHOD FOR DETERMINING STEEL CORROSION COEFFICIENTS IN LEAD - Oleg Golosov (Research institute of nuclear materials, (INM JSC))

10:40 Impact of Cladding Material on Neutronic Balance in Breed-and-Burn fast reactors - Toru Obara (Tokyo Institute of Technology)

10:40 Irradiation Effects of T91 Ferritic/Martensitic Steel - Junhong LI (China Institute of Atomic Energy)

10:40 Irradiation-Thermo-Mechanical Coupling Analysis and Calculation of Fast Neutron Oxide Fuel Element - Qidong CHEN (+86(010)69359493)

10:40 HEAT TRANSFER CALCULATION AND SERVICE LIFE TIME ESTIMATION OF SUBMERGED ELECTROMAGNETIC PUMP FOR LIQUID LEAD - Valeriia Federiaeva (JSC "NIIEFA")

10:40 Influence of preheating temperature on delta-ferrite formation and mechanical properties of 12%Cr steel weld metals - Dong Wu

10:40 ON MEASUREMENT OF OXYGEN CONCENTRATION IN SODIUM BY MEANS OF PLUG INDICATOR - Nikolai Loginov

13:40 Analysis of sodium fire accident after upgrade of ventilation system of primary loop’s corridor - jiayin yang

13:40 Increase of nuclear power plant hydrogen safety using zirconium accumulator - Ekaterina Orlova

13:40 Development of in-vessel source term evaluation method for ULOF events in sodium-cooled fast reactor - Hiroki Sonoda (Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R))

13:40 Experimental and Numerical Study on Temperature Fluctuation in The Upper Plenum of Fast Reactor - Yongqi Du (North China Electric Power University)

13:40 Study on Sodium Fire PSA Methodology for Pool-Type Sodium cooled Fast Reactor - Jing WANG (China Institute of Atomic Energy)

13:40 Fast Reactor Source Term Modeling and Simulation Functional Requirements and Gap Assessment - Shayan Shahbazi (Argonne National Laboratory)

13:40 Development of the Simplified Radionuclide Transport (SRT) Code Version 2.0 for Versatile Test Reactor (VTR) Mechanistic Source Term Calculations - David Grabaskas (Argonne National Laboratory)

13:40 Model validation of the ASTERIA-SFR code related to freezing phenomena of liquid and liquid/particle mixtures based on THEFIS experimental results - Tomoko Ishizu (Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R)) Satoshi Fujita (Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R))

13:40 Preliminary Shielding Analysis for the Versatile Test Reactor - Tingzhou Fei (Argonne National Laboratory)

13:40 SIMULATION OF THE FAST FLUX TEST FACILITY LOSS-OF-FLOW WITHOUT SCRAM ACCIDENT SCENARIO USING THE SAM COMPUTER CODE - Brent Hollrah (Texas A&M University)

13:40 Thermal Hydraulic Simulation of Loss of Flow Without Scram Test in FFTF using DYANA-P code - Vikram Govindarajan (IGCAR)

13:40 Modelling of radionuclide release from primary system during a hypothetical severe accident in an SFR - PARTHKUMAR RAJENDRABHAI PATEL (Indira Gandhi Centre for Atmoc Research, India)
10:40
10:40 - 12:40
Contributions

10:40 Overview of the Versatile Test Reactor Safety Analysis - Tyler Sumner (Argonne National Laboratory)

10:52 Integrating safety at the first design stages: a new methodology for safety-oriented SFR core design - Jean-Baptiste Droin (CEA Cadarache)

11:04 Thermal hydraulic assessment of the performance of secondary sodium system based decay heat removal circuit - anurag samantara (Indira Gandhi Centre for Atomic Research)

11:16 PRE-DESIGN OF A PASSIVE DECAY HEAT REMOVAL SYSTEM WITH A PHASE CHANGE MATERIAL FOR SMR-SFR - Alessandro Pantano (CEA)

11:28 Development of the Versatile Test Reactor (VTR) Probabilistic Risk Assessment - Jason Andrus (Idaho National Laboratory)

11:40 ANALYSIS OF THE SGTR ACCIDENT FOR SAFETY JUSTIFICATION OF TWO-CIRCUIT LEAD COOLED REACTOR. - IURII SHVETSOV (JSC "PRORYV")

11:52 Design Studies Towards Raising FBTR to Full Power - RAGHUPATHY S. (Indira Gandhi Centre for Atomic Research, Kalpakkam)

12:04 Modelling of postulated reactivity insertion in a Generation IV Molten Salt Reactor - Thibault LE MEUTE (CEA Cadarache - LPSC-IN2P3-CNRS)
10:40 - 12:40
Contributions

10:40 The initial stage of closing the NFC of two-component nuclear power. Challenges and solutions - Andrey Gulevich (IPPE JSC)

10:52 Presentation of the new European project PUMMA devoted to Plutonium management in the whole fuel cycle - nathalie chauvin (CEA)

11:04 Fuel cycle closure for high power fast neutron reactor - Elena Rodina (JSC "Proryv")

11:16 Perspectives and discussions on the modes and development path of China's commercial closed nuclear fuel cycle - MIN XIAO (China Nuclear Power Technology Research Institute)

11:28 Potential Role of Fast Reactors with Heterogeneous Fuel Assembly in Development Nuclear Power Structure - Yaroslav Kotov (National Recearch Centre "Kurchatov Institute")

11:40 Reference Fuel Options for Generation-IV Sodium-cooled Fast Reactors - Frédéric SERRE (Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA))

11:52 The influence of isotopic composition of plutonium in fast reactor fuel on the reactivity margin - Yulia Karazhelevskaia

12:04 RADIATION AND HYGIENE ASSESSMENT OF EXTERNAL EXPOSURE FACTORS OF PERSONNEL WORKING AT EXPERIMENTAL FACILITIES IN THE PRODUCTION OF MIXED NITRIDE URANIUM-PLUTONIUM FUEL - Pavel Gantsovsky (Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency)
10:40 - 12:40
Contributions

10:40 Creep and Creep-Fatigue Behavior of an Advanced Stainless Steel (Alloy 709) - Application to Sodium-Cooled Fast Reactors - Abdullah Alomari (King Abdulaziz City for Science and Technology)

10:52 Development of Plasma Nitriding as alternate hardfacing technique for Large components of FBR and Assessment of static In-Sodium Stability of Plasma Nitrided Layer - R. Mythili (IGCAR)

11:04 A novel method of manufacturing a heavy integrated support ring in fast reactor - Sun Mingyue (Institute of Metal Research, Chinese Academy of Sciences) Xu Bin (Institute of Metal Research, Chinese Academy of Sciences) Xie Bijun (Institute of Metal Research, Chinese Academy of Sciences) Li Dianzhong (Institute of Metal Research, Chinese Academy of Sciences)

11:16 Material Data Acquisition Activities to Develop the Material Strength Standard for Sodium-cooled Fast Reactors - Kodai Toyota (Japan Atomic Energy Agency)

11:28 The δ-ferrite transformation behavior and mechanical properties of 316H weld metal during high temperature service - Shitong Wei

11:40 STATE OF DEVELOPMENT OF LEAD COOLANT TECHNOLOGY COMPONENTS FOR BREST-OD-300 REACTOR - Alexander Orlov

11:52 Tensile testing of sub-sized T91 and 316L steel specimens in liquid lead - Kamil Tucek (European Commission, Joint Research Centre)

12:04 New ASTRID SFR - Intermediate Heat Exchanger (IHX) and internal vessel interface system: qualification tests onto a scale 1 representative mock-up - Antony WOAYE HUNE (Framatome) Alejandro MOURGUES (Framatome) Remi MORITZ (Framatome) Alexandre Villedieu (Framatome) Marie-Sophie Cheneau (French Commission for Atomic Energy and Alternative Energy)
10:40 - 12:40
Contributions

10:40 Comparison of calculation methods for lead cooled fast reactor reactivity effects - Máté Szieberth (Budapest University of Technolgoy and Economics)

10:52 Neutronics analysis of CEFR Start-up tests at IGCAR using FARCOB and ERANOS 2.1 Code Systems - Abhitab Bachchan (Indira Gandhi Centre for Atomic Research, Kalpakkam, India)

11:04 Verification of the SPL module of the neutron diffusion code AZNHEX through Neutronics Benchmark of CEFR Start-Up Tests - Roberto Lopez-Solis (National Institute for Nuclear Research)

11:16 Objectives and Status of Neutronics Sub-exercises of the OECD/NEA Benchmark for Uncertainty Analysis in Modelling for Design, Operation and Safety Analysis of SFRs - Friederike Bostelmann (Oak Ridge National Laboratory)

11:28 REALISATION OF AN ADJUSTED NUCLEAR DATA LIBRARY BASED ON ENDF/B-VIII.0 NUCLEAR DATA EVALUATIONS FOR THE ALFRED CORE - donato maurizio castelluccio (ENEA, Bologna, Italy)

11:40 Spatial interdependence of safety related effects in ESFR-SMART core - Jiri Krepel (Paul Scherrer Institut)

11:52 The solution of nuclide kinetic equation for fast reactor in the OpenBPS code with options of choosing calculation method and uncertainties analysis. - Ivan Bukhtiiarov

12:04 Study on actinide conversion capabilities of Molten Salt Reactors (MSR) - Laura Mesthiviers (LPSC/IN2P3/CNRS)
12:40

12:40 - 13:40
13:40
13:40 - 15:40
Contributions

13:40 The Westinghouse Lead Fast Reactor: overview and progress in development - Paolo Ferroni

13:52 Pilot Demonstrational Fast Reactor with Lead Coolant BREST-OD-300 - V.V. Lemekhov (JSC NIKIET)

14:04 CHOICE OF A COOLANT FOR A MODULAR SMALL POWER REACTOR SVBR-100 - Georgii Toshinskii (JSC “AKME-engineering”) Georgii Toshinskii

14:16 Core Design of 100MWe Advanced Nitride-fueled Simplified Liquid Metal Cooled Fast Reactor - Tung Dong Cao Nguyen (Ulsan National Institute of Science and Technology)

14:28 Novel neutronics design of the MYRRHA core - Luca Fiorito

14:40 Project of a multipurpose lead reactor with a hard neutron spectrum - Samokhin Dmitrii (National Research Nuclear University МЕРhI)

14:52 Proposal of a compact core design for the 1000 MWe French commercial Sodium Fast Reactor by means of the SDDS multi-objective optimization tool - Sandra POUMEROULY (EDF)

15:04 Conceptual design of ultra-long life hybrid micro modular reactor cooled by potassium heat pipe - Seongdong Jang (Korea Advanced Institute of Science and Technology (KAIST))
13:40 - 15:40
Contributions

13:40 Coupled neutronic/thermal-hydraulic simulation of Unprotected Loss of Flow Test at Fast Flux Test Facility - Mikityuk Konstantin (Paul Scherrer Institute)

13:52 MECHANISTIC MODELLING OF AEROSOL EVOLUTION IN AN SFR CONTAINMENT FOLLOWING A HYPOTHETICAL SEVERE ACCIDENT - PARTHKUMAR RAJENDRABHAI PATEL (Indira Gandhi Centre for Atmoc Research, India)

14:04 Modelling and Simulation of Source Term for Sodium-Cooled Fast Reactor under Hypothetical Severe Accident: Primary System/Containment System Interface Source Term Estimation - Yuichi ONODA (Japan Atomic Energy Agency)

14:16 Modeling and Simulation of Source Term for Sodium-Cooled Fast Reactor under Hypothetical Severe Accident: Sodium Fire and Radionuclide Transport in Containment - Jong E. Chang (TerraPower, LLC)

14:28 The Severe Accident Management of the high-power SFR with loss of the heat removal from the core - Ilia Pakhomov

14:40 Over three decades of radiological protection experience at Fast Breeder Test Reactor (FBTR) - Sarangapani Rajagopalan (Indira Gandhi Centre for Atomic Research, Kalpakkam)

14:52 Safety Analysis of Small Modular Sodium Fast Reactors in Anticipated Transients Without Scram Scenarios - Xin Jin

15:04 The Versatile Test Reactor (VTR) Approach to Sodium Fire Hazards Analysis and Protection System Methodology - Matthew Bucknor (Argonne National Laboratory)
13:40 - 15:40
Contributions

13:40 Complex of experimental facilities for design and safety justification of fast reactors with liquid metal coolants - Iuliia Kuzina (IPPE JSC)

13:52 Physical modeling of hydrodynamics and heat exchange in fast reactors with liquid metal coolants - Julia Kuzina (SSC RF - IPPE)

14:04 Overview of a Sodium Fast Reactor Thermal Hydraulic Test Facility - Matthew Weathered

14:16 Overview of the R&D programs led by the past at IRSN on sodium fire - Jean-Marc SUCH (IRSN)

14:28 Mechanisms Engineering Test Loop (METL) Facility - Christopher Grandy (Argonne National Laboratory)

14:40 EXPERIMENTAL CAPABILITIES OF THE RESEARCH REACTOR FACILITY MBIR. MAIN AREAS OF THE RESEARCH PROGRAMME IN THE INTERESTS OF THE GENERATION 4 REACTORS - Dmitrii Klinov

14:52 Versatile Test Reactor (VTR) Project Mission and Status - Jordi Roglans-Ribas (Argonne National Laboratory)

15:04 MULTIPURPOSE RESEARCH FACILITY MBIR AND POLY FUNCTIONAL RADIOCHEMICAL COMPLEX (R&D COMPLEX) AS A UNIQUE RESEARCH PLATFORM - Alexander Zagornov (Rosatom)

15:16 VERSATILE TEST REACTOR: CONCEPTUAL CORE DESIGN OVERVIEW - Florent Heidet (Argonne National Laboratory)
13:40 - 15:40
Contributions

13:40 Possibility of Simulating Natural Circulation in Fast Neutron Reactors Using a Light Water Test Facility - Dmitrii Uralov

13:52 Recent thermal hydraulic studies of Gas Fast Reactor demonstrator ALLEGRO - Boris Kvizda (VUJE, a.s.)

14:04 Experimental modeling of a fuel element simulator vibration in a coolant flow - Nikolaay Pribaturin (IBRAE RAN, Novosibirsk division)

14:16 DEVELOPMENT OF COOLANT VOIDING MODEL FOR FAST REACTOR CORE - Dhrumil Ganatra

14:28 ALFRED FLOW BOCKAGE ANALYSIS - Ivan Di Piazza (ENEA Brasimone R. C.)

14:40 CFD Simulations on a hexagonal 61-pin wire-wrapped fuel bundle with STARCCM+ and comparison with experimental data. - Octavio Bovati (Texas A&M)

14:52 Progress in system thermohydraulic code HYDRA-IBRAE/LM models development for fast reactor simulation - Alexander Palagin (Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN))
15:40

15:40 - 15:50

15:50

15:50 - 17:00
Thursday, 21 April 2022

09:30

09:30 - 10:30

10:30

10:30 - 10:40
10:30 - 17:00
Contributions

10:40 VERSATILE TEST REACTOR: CORE SYSTEM DESIGN REQUIREMENTS TO SUPPORT ADVANCED REACTOR DEVELOPMENT - Adam Nelson (Argonne National Laboratory)

10:40 Conceptual Core configuration for increasing Power of Fast Breeder Reactor to 40 MWt - RAGHUKUMAR Ganapathy (Indira Gandhi Cenre for Atomic Research)

10:40 ALFRED DHR system scaling verification and numerical pre-test analysis - Marco Caramello (Ansaldo Nucleare)

10:40 RADIATION-HYGIENIC ASSESSMENT OF INTERNAL EXPOSURE FACTORS OF PERSONNEL WORKING AT EXPERIMENTAL FACILITIES IN THE PRODUCTION OF MIXED NITRIDE URANIUM-PLUTONIUM FUEL - Andrey Karev (Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency)

10:40 Cognitive Information Retrieval Based on Ontological Model of Knowledge Representation - Nikolay Maksimov (National research nuclear university (Moscow Engineering Physics Institute))

10:40 INVESTIGATION OF THE SOLUBILITY OF ACTINIDE FLUORIDES FOR THE CHOICE OF A SALT SOLVENT FOR A MOLTEN-SALT REACTOR-BURNER OF MINOR ACTINIDES - Полина Санникова

10:40 Experiment-calculated method for determination of prompt neutron lifetime in fast metal cores intended for verification of neutron transfer simulation codes - Sergey Andreev

10:40 Revealing the dependencies of partitioning americium-241 and uranium using sorption technology based on solid-phase extractant TODGA - Aleksandr Savelev (National Research Nuclear University MEPhI; Leading Research Institute of Chemical Technology (VNIIKhT))

10:40 JUSTIFICATION OF CRITICAL EXPERIMENTS ON STAND FKBN-2 TO VERIFY NEUTRON-PHYSICAL SOFTWARE FOR CALCULATIONS OF THE MOLTEN-SALT REACTOR - Mikhail Trapeznikov

10:40 Eddy Current Flow Meter flow rate measurements in liquid Sodium at the SUPERFENNEC loop - Gunter Gerbeth (Helmholtz-Zentrum Dresden - Rossendorf)

10:40 Evaluation of EPDM and Silicone rubber compounds for application in Reprocessing Plant - Ananthasivan Krishnamurthy (IGCAR, DAE)

10:40 COMPLEX RADIATION AND HYGIENE STUDIES OF RADIATION IMPACT FACTORS ON PRODUCTION PERSONNEL, MIXED NITRIDE URANIUM-PLUTONIUM FUEL FOR FAST NEUTRON REACTORS - Alexander Samoylov (Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency,)

10:40 Design, manufacturing and transportation of high capacity High Level Liquid Waste Storage tanks - Kumst Dhananjeya

10:40 Experimental investigation of the fluid-structure interaction effect between adjacent equipment supports in a fast reactor - Dexuan Duan (North China Electric Power University)

13:40 Transmutation efficiency of minor actinides in fast-and thermal-spectrum molten salt reactors - O. Ashraf (Institute of Nuclear Physics and Engineering, National Research Nuclear University MEPhI, 115409, Russian Federation, Kashirskoye Shosse, 31)

13:40 R&D on recovery and separation of americium and curium under "Proryv" project - Vitali Vidanov (JSC "Proryv")

13:40 Controlled thermonuclear fusion: potential role of a joint (Th-U-Pu) nuclear fuel cycle - Evgeny Kulikov (National Research Nuclear University MEPhI)

13:40 Transmutation of minor actinides in a fast reactor with uranium-curium fuel - Anna Terekhova

13:40 Determination of the metallic and oxide compounds in models based on metallic uranium containing uranium dioxide, metallic neodymium, cerium as well as neodymium and cerium oxides - Yury Zaikov (Institute of High Temperature Electrochemistry of the Ural Branch of the Russian Academy of Sciences)

13:40 Electrical conductivity of multicomponent chloride melts, containing ions of mono-, di-, and trivalent metals - Alexei Potapov (Institute of High Temperature Electrochemistry)

13:40 Reprocessing of nitride and metallic spent nuclear fuel using molten salts - Alexei Potapov (Institute of High Temperature Electrochemistry)

13:40 Optimization of Ruthenium concentration in PUREX Process during Fast reactor fuel Reprocessing - Ananthasivan Krishnamurthy (IGCAR, DAE)

13:40 Development of density control technologies for MOX pellet using dry recycled powders - Masahiro Nishina

13:40 Electrolytic reduction of the simulated oxide spent nuclear fuel in LiCl-Li2O melt - Alexander Dedyukhin (Institute of High Temperature Electrochemistry of the Ural Branch of the Russian Academy of Sciences)

13:40 Comparative analysis of minor actinides transmutation in a molten-salt burner reactor based on LiF-NaF-KF and LiF-BeF2 salts - Mikhail Belonogov (RFNC-VNIITF named after academ. E.I. Zababakhin)

13:40 Removal of Radiocesium from High-Level Liquid Waste using Inorganic Ion-exchangers - Anshul Kumari (Waste Immobilization Plant, Integrated Nuclear Recycle Plant, Nuclear Recycle Board, Bhabha Atomic Research Centre, Kalpakkam 603 102, India)

13:40 Development of Artificial Intelligence through PLC & SCADA to predict process related failure and abnormality in a Reprocessing Plant - Ananthasivan Krishnamurthy (IGCAR, DAE)

13:40 Assay of Waste drum based on Passive Neutron Counting Technique - Sivakumar P
10:40
10:40 - 12:40
Contributions

10:40 Recent studies on fuel properties and irradiation behaviors of Am/Np-bearing MOX - Shun Hirooka (Japan Atomic Energy Agency)

10:52 Selection, testing and development of qualification procedure for ALLEGRO gas-cooled fast reactor fuel - Zoltán Hózer (Centre for Energy Research)

11:04 Design of metal fuel pin for test irradiation in FBTR and for future reactors. - RAJKUMAR THIRUNAVUKKARASU (IGCAR)

11:16 Development of simplified fuel fabrication technologies for fast reactors - Tomoomi Segawa (Japan Atomic Energy Agency)

11:28 Advanced Reactor Experiments for Sodium Fast Reactor Fuels (ARES) Project: Transient Irradiation Experiments for Metallic and MOX Fuels - Colby Jensen (Idaho National Laboratory)

11:40 Towards design guidelines for fast reactor oxide fuel pins with high Pu content: driving post irradiation examination by benchmarking European fuel performance codes - Victor BLANC (French Atomic Energy Commission)

11:52 Root Cause Analysis of FBTR Failed Fuel Pin - NAGA SIVAYYA DUDALA (IGCAR, Kalpakkam)

12:04 Uranium and mixed uranium-plutonium nitrides thermal stability - Mikhail Krivov (Joint Stock Company "A.A. Bochvar High-technology Research Institute of Inorganic Materials")
10:40 - 12:40
Contributions

10:40 Estimation of mean charge on sodium metal aerosol in the argon and nitrogen gas environment during external gamma irradiation - Amit Kumar (Radiological and Environmental Safety Division, IGCAR, Kalpakkam-603102, India.)

10:52 THERMOHYDRAULIC TESTS IN JUSTIFICATION OF DESIGN CHARACTERISTICS OF THE BREST-OD-300 RP STEAM GENERATOR - Iuliia Kuzina (IPPE JSC)

11:04 Experimental and computational studies of heat exchange for liquid metals boiling in fuel assembly models at accidental conditions - Julia Kuzina (SSC RF - IPPE)

11:16 Investigation on natural circulation for decay heat removal in reactor vessel of sodium-cooled fast reactor - Kosuke Aizawa (Japan Atomic Energy Agency)

11:28 Coolant flow monitoring with an Eddy Current Flow Meter at a mock-up of a liquid metal cooled fast reactor - Nico Krauter (Helmholtz-Zentrum Dresden-Rossendorf)

11:52 Overview of critical experiments with fast metal cores held on assembly machine FKBN-2 - Yuri Sokolov

12:04 AN EXPERIMENTAL STUDY ON SECONDARY SODIUM SYSTEM BASED DECAY HEAT REMOVAL CIRCUIT OF A SODIUM COOLED FAST REACTOR - S.P Pathak (IGCAR)
10:40 - 12:40
Contributions

10:40 Codes of new generation – sustainable platform for numerical modeling of installations in the Proryv project - Nastasia Mosunova (Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN))

10:52 Dutch Thermal Hydraulic Design and Safety Support for LMFRs - Ferry Roelofs (NRG)

11:04 Verification of SARAX Code for the Transient Analysis of Sodium-cooled Fast Reactor - Xiaoqian JIA

11:16 Phénix Control Rod Withdrawal test analysis using a multiphysics methodology - Barbara FORNO (CEA Cadarache)

11:28 Simulation of FFTF Individual Reactivity Feedback Tests with SAS4A/SASSYS-1 Code - Anton Moisseytsev (Argonne National Laboratory)

11:40 Current status of development of 3D DNS CONV-3D code: one- and two-phase flow models - Vladimir Chudanov (IBRAE RAN)

11:52 Development of Multi-level Simulation System for Core Thermal-hydraulics Coupled with Plant Dynamics Analysis - Prediction of Transient Temperature Distribution in a Subassembly under Inter-subassembly Heat Transfer Effect - - Norihiro Doda (Japan Atomic Energy Agency)

12:04 Development of SFR core degradation simulation code SIMMER-V and its validation & verification studies - Elena Martin Lopez (CEA)
12:40

12:40 - 13:40
13:40
13:40 - 15:40
Contributions

13:40 FEASIBILITY STUDY OF HETEROGENEOUS TRANSMUTATION OF AMERICIUM IN FAST REACTORS - Andrey Gulevich (IPPE)

13:52 The role of pyrochemical processing in a NetZero economy in the UK - Michael Edmondson (The National Nuclear Laboratory)

14:04 Fabrication and reprocessing of mixed uranium-plutonium nitride fuel for reactor BREST - Andrei Shadrin (JSC "Proryv")

14:16 HETEROGENEOUS BURNING OF MINOR ACTINIDES IN A FAST REACTOR - Alexander Tuzov (JSC "SSC RIAR")

14:28 Advanced Flow-Sheet for Partitioning of Trivalent Actinides from Fast Reactor High Active Waste - desigan narasimhan (IGCAR, DAE)

14:40 Multi-criteria comparison of the efficiency of minor actinides burning in different nuclear reactors based on the INPRO/IAEA KIND approach - Stepan Kviatkovskii (SC Rosatom)

14:52 Physical feasibility of MA transmutation in a two-component nuclear energy system in Russia - Yury Khomyakov (Private institution «Innovation and technology center for the «PRORYV» project»)

15:04 Investigation of the anodic processes on the ceramic anode in the oxide-chloride melts - Alexander Dedyukhin (Institute of High Temperature Electrochemistry of the Ural Branch of the Russian Academy of Sciences)
13:40 - 15:40
Contributions

13:40 Models of the integral EUCLID/V2 code for numerical simulation of severe accidents in a sodium-cooled fast reactor with MOX and MNUP fuels - Eduard Usov (IBRAE RAN)

13:52 Development of Integrated Severe Accident Analysis Code, SPECTRA for Sodium-cooled Fast Reactor - Akihiro Uchibori (Japan Atomic Energy Agency)

14:04 Aerosol module for modeling of the fission product behavior in FR cooling circuits and NPP compartments - Andrey Sorokin (IBRAE, Moscow, Russia)

14:16 Analysis of the natural circulation capacity of decay heat removal system in pool-type sodium-cooled fast reactor - Yapeng Liu (Xi'an Jiaotong University)

14:28 Regulatory Perspectives on Analytical Codes and Methods for Advanced Reactors - Walter Klein-Heßling

14:40 Models of the integral EUCLID/V2 code for numerical modeling of different regimes of lead-cooled fast reactor - Dmitry Veprev (NSI RAS)

14:52 Target Accuracy Requirements and an evidence-based background for MSFR safety assessment - Evgeny Ivanov (IRSN)

15:04 SOCRAT-BN INTEGRAL CODE: DEVELOPMENT, VALIDATION AND CURRENT STATUS - Ruslan Chalyy (IBRAE RAS)
13:40 - 15:40
Contributions

13:40 TRAINING OF NEW GENERATION SPECIALISTS IN THE FIELD OF FAST NEUTRON REACTORS AND NUCLEAR FUEL CYCLE CLOSURE - Georgy Tikhomirov (NRNU MEPhI)

13:52 An e-learning tool on Fast Reactors and their Fuel Cycles - Nicholas Barron (National Nuclear Laboratory)

14:04 GEN IV INTERNATIONAL FORUM WEBINARS INITITATIVE - Patricia Paviet (Pacific Northwest National Laboratory)

14:16 Preserving and transferring knowledge in the field of fast reactor technologies. Experience of the Obninsk Institute of Nuclear Power Engineering MEPhI - Aleksandr Nakhabov (Obninsk Institute for Nuclear Power Engineering NRNU MEPhI)

14:28 Investigation on Human Resources Needs and Competences Building for ALFRED Implementation in Romania - Minodora APOSTOL (RATEN ICN)

14:40 Overview of IAEA Fast Reactor Related Technology Development Activities - Joseph Mahanes (IAEA)
15:40

15:40 - 15:50

15:50

15:50 - 17:00
Friday, 22 April 2022
10:30
10:30 - 12:30
Contributions

10:30 Sketch Design of Fuel Sub-Assemblies for a SFR-150 MWe - Thierry BECK (CEA)

10:42 OPTIMIZATION OF BUILT-IN PRIMARY SODIUM PURIFICATION SYSTEM FOR ADVANCED BN REACTOR PLANT - Sergey Rukhlin (JSC “Afrikantov OKBM”)

10:54 DESIGN & ANALYSIS OF A NOVEL ARRANGEMENT FOR COUPLING AND DECOUPLING OF ROTATABLE PLUGS IN PFBR - Jagruti Mote (Reactor Design & Technology group, Indira Gandhi centre for Atomic Research)

11:06 Optimization of the secondary loops on the ESFR SMART project - joel guidez (CEA)

11:18 Design of secondary sodium based decay heat removal system for future fast breeder reactors - Pritam Kumar Patel (Indira Gandhi Centre for Atomic Research)

11:30 Integration of Small Modular Lead Fast Reactor with Energy Storage for load-following operation in high V-RES penetration electricity markets - Marco Caramello (Ansaldo Nucleare)

11:54 Evaluation of an increase of the power density for the French commercial Sodium Fast Reactor and optimization study at 1100 MWe with the SDDS tool - Delphine Gérardin (EDF)

12:06 iMAGINE - a Breakthrough Technology for Closing the Fuel Cycle without Reprocessing - Bruno Merk (University of Liverpool)
10:30 - 12:30
Contributions

10:30 Development of methodology to evaluate mechanical consequences of vapor expansion in SFR severe accident transients: lessons learned from previous France-Japan collaboration and future objectives and milestones - Andrea Bachrata (CEA)

10:42 Simulation of ULOF initiation phase in ESFR-SMART with SIMMER-III - Xue-Nong Chen (Karlsruhe Institute of Technology (KIT), Institute for Nuclear and Energy Technologies (IKET))

10:54 The SAIGA in-pile experimental program to qualify the SIMMER calculation tool in SFR Severe Accident Conditions - Frédéric Payot (CEA : Commissariat à l’Energie Atomique et aux Energies Alternatives)

11:06 A Status of Experimental Program to Achieve In-Vessel Retention during Core Disruptive Accidents of Sodium-Cooled Fast Reactors - KENJI KAMIYAMA (Japan Atomic Energy Agency)

11:18 Comparisons of Feedback under UTOPA with In Pin Fuel Motion Dynamics in Fast Reactors - Sathiyasheela T. (IGCAR, India)

11:30 French-Japanese experimental collaboration on fuel-coolant interactions in sodium-cooled fast reactors - Christophe Journeau (CEA)

11:42 Transient 3D simulations for the ASTRID reactor: preliminary results for the ULOF initiation phase - Simone GIANFELICI (ENEA)

11:54 Experiment and Numerical Simulations on SFR Core-catcher Safety Analysis after Relocation of Corium - Xiaoyang Gaus-Liu (Karlsruhe Insitute of Technology)
10:30 - 12:30
Contributions

10:30 DIGITAL TECHNOLOGIES FOR PROJECT DEVELOPMENT ODEC AND PEC AND DIGITAL TWINS - Andrei Fedorovskii

10:42 Development of an Artificial Neural Network for predicting spatial interdependencies of reactivity effects in Sodium Fast Reactors - Antonio Jiménez-Carrascosa1 (Politécnica de Madrid (UPM))

10:54 APPLICATION OF DIGITAL TWIN OF FAST REACTOR PLANT FOR CONTROL SYSTEM ALGORITHM TESTING - Anton Ushatikov

11:06 Computational Studies of Advantages of Lead-Cooled Fast Reactor Core - A.V. Moiseev (JSC NIKIET)

11:18 Passive Heat Removal System Analysis for the Westinghouse Lead Fast Reactor - Daniel Wise

11:30 APPROACHES TO FORM THE BN 1200 CORE START LOADING USING MOX-FUEL AND MNUP-FUEL - Sergey Belov

11:42 DISTINCTIVE FEATURES OF THE BN-800 CORE IN THE COURSE OF TRANSITION TO COMPLETE MOX-FUEL LOADING - Sergey Belov
Poster Session
Poster Session
10:30 - 15:30
Contributions

10:30 DEVELOPMENT OF THE TECHNICAL APPROACH FOR RESEARCH OF THE SODIUM COOLANT CURRENT IN THE INTEGRAL TYPE REACTOR - Sergei Rogozhkin (JSC “Afrikantov OKBM”)

10:30 ELABORATION OF THE THERMAL-HYDRAULIC CHARACTERISTICS OF THE REACTOR PLANT BASED ON THE OPERATION EXPERIENCE OF THE POWER UNIT WITH BN-800 REACTOR - Ilia Fadeev

10:30 Application of Model Based System Engineering in Design of Digital Fast Reactor Nuclear Power Plant - Guo Yujie

10:30 Modeling of the coolant region in the ALFRED core in case of thermal expansion - Roberto Pergreffi (ENEA)

10:30 CRITICALITY SENSITIVITY ANALYSIS IN RELATION TO EMPTIES OF A FAST REGENERATOR NUCLEAR REACTOR - Joao Claudio Fiel (IME)

10:30 Study on the Method of Correction of Fast Reactor Power Distribution by MCNP - Xiaochun JIA (CIAE)

10:30 COMPARATIVE ANALYSIS OF CALCULATIONAL AND EXPERIMENTAL DIFFERENCES OF THE NEUTRON-PHYSICAL CHARACTERISTICS OF THE BN-800 REACTOR - Viacheslav Mishin (State Scientific Centre of the Russian Federation – Leypunsky Institute for Physics and Power Engineering, Joint-Stock Company" IPPE JSC)

10:30 Integrated thermal hydraulic analysis of Hot and Cold Pools of a liquid sodium cooled 600 MWe fast reactor - Ram Kumar Maity (Indira Gandhi Center for Atomic Research)

10:30 Software for Simulation of Fast Reactor Operation in a Closed Nuclear Fuel Cycle (SC RTM-2) - Ivan Popov

10:30 Characterization of the Molten Chloride Fast Reactor fuel cycle options - Jiri Krepel (Paul Scherrer Institut)

10:30 ENDF/B-VIII.0 NUCLEAR DATA SENSITIVITY AND UNCERTAINTY (S/U) ANALYSIS OF KEY SAFETY-RELEVANT REACTIVITY COEFFICIENTS FOR THE ALFRED CORE - donato maurizio castelluccio (ENEA) francesco lodi (ENEA) vincenzo giuseppe peluso (ENEA) giacomo grasso (ENEA) massimo sarotto (ENEA)

13:30 The Code Complex for Computational Evaluation of Technical Solutions and Optimization of Processes Parameters of CNFC - Inga Makeeva (FSUE "RFNC-VNIITF")

13:30 Mitigation of Sloshing Effects in High level Liquid Waste (HLW) Storage Tank for Nuclear Spent Fuel Applications - Ananthasivan Krishnamurthy (IGCAR, DAE)

13:30 ADS for Energy Production and 233U breeding in HEU-Thorium Oxide system - Ahmed Ali (EGYPTIAN ATOMIC ENERGY AUTHORITY)

13:30 Neutronic Calculation of CEFR Core using Different Nuclear Data Libraries - Andreea Moise (Institute for Nuclear Research Pitesti)

13:30 Integral code COMPLEX for radiation safety assessment of reactor and nuclear fuel cycle facilities - Valerii Bereznev (Nuclear Safety Institute the of Russian Academy of Sciences)

13:30 Calculation of the materials activation with BPSD code - Alexander Belov (Nuclear Safety Institute the of Russian Academy of Sciences)

13:30 Verification and validation of the CEFR Serpent model for the generation of reference solutions and Cross Sections database for the deterministic code AZNHEX - Roberto Lopez-Solis (National Institute for Nuclear Research)

13:30 Research on the Impact of Advanced Rule Design System on the Digitization of Reactor Building Model - Jin Wang Hongyi YANG

13:30 Мodeling of water leak into sodium in the BN-600 steam generator - Olga Miazdrikova (Scientific Centre of the Russian Federation – Leypunsky Institute for Physics and Power Engineering, Joint-Stock Company" (IPPE JSC))

13:30 Some results of using partial equations for calculations of transient processes in fast breeder reactors - Evgeny Seleznev (All-Russian Research Institute for Nuclear Power Plants Operation)

13:30 Thermodynamic simulation of the oxidation processes at the reprocessing of spent nuclear fuel in the LiCl-KCl melt - Alexei Potapov (Institute of High Temperature Electrochemistry)
12:30

12:30 - 13:30
13:30
13:30 - 15:30
Contributions

13:30 ON THE POSSIBILITY TO CHANGE THE ISOTOPIC COMPOSITION OF PLUTONIUM FROM THE SPENT MOX FUEL OF PWRs IN FAST REACTORS - Andrey Gulevich (IPPE)

13:42 Postirradiation characterization of AFC metallic fuel alloys concepts. - Luca Capriotti (Idaho National Laboratory)

13:54 RESULTS OF POST-IRRADIATIONS EXAMINATIONS OF MIXED NITRIDE PINS WITH GAS AND LIQUID METAL SUB-LAYERS - Anna Belyaeva (Joint Stock Company «State Scientific Center – Research Institute of Atomic Reactors» (JSC «SSC RIAR»))

14:06 Nuclear Fuels for Fast Reactors-A Review - Abu Baker Maqbool (PAEC)

14:18 LOW ENRICHMENT NUCLEAR FUEL BASED ON URANIUM-ZIRCONIUM CARBONITRIDE: REACTOR TESTS AND PREPARATION FOR STUDIES AT CRITICAL ASSEMBLIES - Andrei Bakhin (LUCH Research and Production Association, Research and Development Institute, Federal State Unitary Enterprise)

14:30 TYPES OF CHEMICAL COMPOUNDS IN THE ASSESSMENT OF RADIATION AND HYGIENIC HAZARDS WHEN WORKING WITH IRRADIATED NITRIDE FUEL - Artem Komarov (Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency)

14:42 Research and development of nuclear fuel for fast neutron reactor - Maksim KHRAMTSOV

14:54 Analysis of Fuel Burnup and Safety Parameters of Gas Cooled Fast Breeder Reactors - Moustafa Aziz Ibrahim (ENRRA)
13:30 - 15:30
Contributions

13:30 ALFRED High priority R&D Needs - Gabriele Firpo (Ansaldo Nucleare SpA)

13:42 Preliminary testing of ALFRED DHR System - Marco Caramello (Ansaldo Nucleare S.p.A.)

13:54 DESIGN, MANUFACTURING AND IN-SODIUM TESTING OF AM350-WELDED DISC BELLOWS FOR FBTR CONTROL ROD DRIVE MECHANISM - S C S P Kumar Krovvidi (IGCAR, kalpakkam)

14:06 Implementation of LFR Experimental Infrastructures in Romania - Daniela Gugiu (RATEN ICN)

14:18 EXPERIMENTAL TEST FACILITY TO TEST A PROTOTYPE OF THE AIR HEAT EXCHANGER GATE FOR THE ADVANCED BN REACTOR PLANT. DESIGN AND CONSTRUCTION ITEMS - Maksim Grushko (JSC “Afrikantov OKBM”)

14:30 France-Japan Collaboration on Thermodynamic and Kinetic Studies of Core Material Mixture in Severe Accidents of Sodium-Cooled Fast Reactors - Andrea Quaini (ISAS, Service de la Corrosion et du Comportement des Matériaux dans leur Environnement (SCCME), CEA, Université Paris-Saclay, F-91191, Gif-sur-Yvette, France)

14:42 Versatile Test Reactor (VTR) Experimental Capabilities - Kevan Weaver (Idaho National Laboratory)

14:54 LFR Design and Technologies Development at ENEA: Status and Perspectives - Mariano Tarantino (ENEA)
13:30 - 15:30
Contributions

13:30 Simulation of fission gas release in the 3-D fuel performance code OFFBEAT - Carlo Fiorina (EPFL, Switzerland)

13:42 First fully adjusted set of parameters for the corrosion product contamination code OSCAR-Na - Jean-Baptiste GENIN (CEA, DES, IRESNE, DTN,)

13:54 MSR Fuel Cycle and Thermo-Dynamics Simulations - Jonathan Dietz (Paul Scherrer Institut )

14:06 The fluid structure interaction of narrow gaps between thin-wall coaxial structures in fast reactors - Yu LIU (North China Electric Power University)

14:18 A statistical design method for steady state creep applied to Grade 91 components - Mark Messner (Argonne National Laboratory)

14:30 Мechanistic code BERKUT-U: self-consistent modeling of fuel rods thermomechanical behavior and processes in the fuel of fast breeder reactors - Anton Zadorozhnyi (Nuclear Safety Institute of the Russia Academy of Sciences (IBRAE RAN))

14:42 Computational fluid dynamics study for estimation of dilution for failed fuel location system - Ram Kumar Maity (Indira Gandhi Center for Atomic Research)
15:30

15:30 - 15:40
15:40
15:40 - 16:20
Contributions

15:40 Chair of Conference International Advisory Committee Closing Remarks - Arun Kumar Bhaduri

16:00 Conference General Co-Chair Closing Remarks - Mikhail Chudakov