-
17:30
Neutronic Self-sustainability of a Breed-and-Burn Fast Reactor Using Super-Simple Fuel Recycling
-
Chihyung Kim
(Korea Advanced Institute of Science and Techology)
-
17:30
A Preliminary Study of P&T Scenario on a Sustainable Energy System in China
-
Yong YANG
(China Institute of Atomic Energy)
-
17:30
Fast Reactors - The Belgian Regulatory Approach
-
Matthias Vanderhaegen
(Federal Agency for Nuclear Control)
-
17:30
Numerical Investigation of Sodium Spray Combustion Test with SPHINCS code
-
Takashi Takata
(Japan Atomic Energy Agency)
-
17:30
Evaluation of Anticipated Transient without Scram for SM-SFR using SAS4A/SASSYS-1
-
Deokjung Lee
(Ulsan National Institute of Science and Technology)
-
17:30
Modeling technologies of fuel cycles
-
Inga Makeyeva
(RFNC-VNIITF)
-
17:30
TRANSMUTATION TRAJECTORY ANALYSIS IN THE MODELLING OF LFR FUEL CYCLE
-
Mikołaj Oettingen
(AGH University of Science and Technology, Faculty of Energy and Fuels, Department of Nuclear Energy)
-
17:30
Modeling of hydrodynamic processes at a large leak of water into sodium in the fast reactor coolant circuit
-
Olga Myazdrikova
(Institute for Physics and Power Engineering named after A.I. Leypunsky” (IPPE))
-
17:30
The way of nitride fuel producing by high voltage electrodischarge compaction
-
Maria Tarasova
(National research nuclear University "MEPhI")
-
17:30
SIBYLLA CODE: ASSESSMENT OF WATER BODIES CONTAMINATION AND DOSES RECEIVED BY POPULATION DUE TO RADIOACTIVITY DISCHARGES INTO THE HYDROSPHERE
-
Alexey Krylov
(Nuclear Safety Institute of Russian Academy of Sciences)
-
17:30
Decay-heat removal in accidents in fast reactors with liquid metal coolant
-
IURII SHVETSOV
(Private institution «Innovation and technology center for the «PRORYV» project»)
-
17:30
Use of ion irradiations to help design of advanced austenitic steels
-
Yann DE CARLAN
(SRMA, CEA Saclay, Université Paris-Saclay, 91191 Gif-sur-Yvette Cedex, France)
-
17:30
Possibility studies of a boiling water cooled traveling wave reactor
-
Xue-Nong Chen
(KIT, IKET)
-
17:30
Experience on MOX fuel fabrication for fast reactor at PFPF
-
Kiichi Suzuki
(Japan Atomic Energy Agency)
-
17:30
Sensors of content of oxygen dissolved in heavy liquid metal coolants
-
Roman Sadovnichiy
(JSC “SSC RF – IPPE”)
-
17:30
Isothermal transformation austenite-ferrite in a P92 steel
-
María Luppo
(Argentina Atomic Energy Commission)
-
17:30
Precipitate phases in a weldment of P92 steel
-
María Luppo
(Argentina Atomic Energy Commission)
-
17:30
Study of isolation valve for Sodium Fast Reactor
-
David Montagnier
(AREVA NP)
Dominique Villani
(AREVA NP)
Gilles Rodriguez
(CEA)
Julien Large
(VELAN SAS)
Marc Gosset
(AREVA NP)
Martin Delmas
(VELAN SAS)
Nicolas Crepin
(VELAN SAS)
-
17:30
New results on the continuous cooling behavior of an ASTM A335 P92 steel
-
María Luppo
(Argentina Atomic Energy Commission)
-
17:30
Study of the austenitization process in a P91 steel
-
María Luppo
(Argentina Atomic Energy Commission)
-
17:30
Thermodynamics and separation factor of lanthanides and actinides in system “liquid metal-molten salt”
-
Valeri Smolenski
(Institute of High-Temperature Electrochemistry UB RAS)
-
17:30
ECOLOGICAL ASPECTS OF THE USE OF FAST REACTORS IN A CLOSED NUCLEAR FUEL CYCLE UNDER THE “PRORYV” PROJECT
-
RUDOLF ALEXAKHIN
(INSTITUTION «ITC «PRORYV» PROJECT»)
-
17:30
Investigations in a substantiation of high-temperature nuclear energy technology with fast-neutron reactor cooled by sodium for manufacture of hydrogen and other innovative applications
-
Aleksandr Sorokin
(SSC RF-IPPE)
-
17:30
Preliminary transient analyses of SEALER
-
Ignas Mickus
(LeadCold Reactors)
-
17:30
On the possibility of using various types of fuel in the MBIR reactor core
-
Pavel Maslov
(SSC RF-IPPE)
-
17:30
The Effect of Proton Irradiation on the Corrosion Behaviors of Ferritic/Martensitic Steel
-
Jeonghyeon Lee
(UNIST)
-
17:30
Thermal hydraulic investigation of sodium fire and hydrogen production in top shield enclosure of an FBR following a core disruptive accident
-
Velusamy Karuppanna Gounder
(Indira Gandhi Centre for Atomic Research)
-
17:30
Numerical and Experimental Investigations of Tube-to-Tube Interaction of Air Heat Exchangers of PFBR under Seismic Excitations
-
Velusamy Karuppanna Gounder
(Indira Gandhi Centre for Atomic Research)
-
17:30
Computational modelling of inter-wrapper flow and primary system temperature evolution in FBTR under extended Station Blackout
-
Velusamy Karuppanna Gounder
(Indira Gandhi Center for Atomic Research)
-
17:30
Model validation of the ASTERIA-FBR code related to core expansion phase based on THINA experimental results
-
Tomoko Ishizu
(Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R))
-
17:30
Multiscale computer modeling of nuclear fuel properties at radiation and thermal impacts
-
Sergey Starikov
(Nuclear Safety Institute of the Russian Academy of Sciences)
-
17:30
The lead-cooled fast reactor transition to equilibrium operating conditions
-
Igor Volkov
(Russian Federal Nuclear Center - All-Russia Research Institute of Technical Physics)
-
17:30
ROUZ CODE: CFD APPROACH FOR ASSESSMENT OF RADIATION SITUATION DURING ATMOSPHERE RADIOACTIVITY RELEASES WITHIN AN INDUSTRIAL SITE
-
Dmitry Blagodatskykh
(Nuclear Safety Institute (IBRAE RAN))
-
17:30
Computational investigation of nuclear waste incineration efficiency in a subcritical molten salt driven by 50-100 MeV protons
-
Seyed Mohammad Mirvakili
(AEOI)
Zohreh Gholamzadeh
(AEOI)
-
17:30
Optimization of the thermomechanical treatment to achieve a homogeneous microstructure in a 14Cr ODS steel
-
Benjamin Hary
(CEA)
-
17:30
Resting Bottom Fast Reactor
-
Didier Costes
(CEA)
-
17:30
The concept of 50-300 MWe modular-transportable nuclear power plant with sodium coolant and a gas turbine
-
Yurij Osheyko
(none)
-
17:30
A High Density Uranium Zirconium Carbonitride LEU Fuel for Application in Fast Reactors
-
S Sikorin
(The Joint Institute for Power and Nuclear Research SOSNY of the National Academy of Sciences of Belarus)
-
17:30
A Mechanistic Source Term Calculation for a Metal Fuel Sodium Fast Reactor
-
David Grabaskas
(Argonne National Laboratory)
-
17:30
Advanced Reactor PSA Methodologies for System Reliability Analysis and Source Term Assessment
-
David Grabaskas
(Argonne National Laboratory)
-
17:30
Advanced Energy Conversion for Sodium-Cooled Fast Reactors
-
James Sienicki
(Argonne National Laboratory)
-
17:30
"Peculiarities of behavior of Coated Particle fuel in the core of Fast Gas Reactor BGR-1000"
-
Aleksei Sedov
(NRC "Kurchatov Institute")
-
17:30
ASTRID hot cells
-
Bernard GUILLOU
(SEIV)
-
17:30
Corrosion behavior of tube steel for BREST-OD-300 steam generator
-
Kirill Shutko
(N.A. Dollezhal Research and Development Institute of Power Engineering)
-
17:30
ASTRID reactor: design overview and main innovative options for Basic Design
-
FREDERIC CHANTECLAIR
(French Alternative Energies and Atomic Energy Commission (CEA))
-
17:30
The UO2– MeO2 (Me = Th, Pu, Zr) cathode crystalline deposits formation during the melts electrolysis.
-
Vladimir Krotov
(Institute of High-Temperature Electrochemistry UB RAS)
-
17:30
3-D Core Design of the TRU-Incinerating Thorium RBWR Using Accident Tolerant Cladding
-
Sandra Bogetic
(University of California at Berkeley)
-
17:30
Americium Retention During Metallic Fuel Fabrication
-
Randall Fielding
(Idaho National Laboratory)
-
17:30
Study on the sensitivity analysis of the installed capacity and the high-level waste generation based on closed nuclear fuel cycle
-
Yun HU
(China Institute of Atomic Energy)
-
17:30
THE CODE ROM FOR ASSESSMENT OF RADIATION SITUATION ON A REGIONAL SCALE DURING ATMOSPHERE RADIOACTIVITY RELEASES
-
Dmitry Dzama
(Nuclear Safety Institute of Russian Academy of Science)
-
17:30
Full-fledged affination extractive-crystallizng platform for technology validation of the fast reactor spent fuel reprocessing on fast neutrons – the results of first experiments
-
Sergei Terentev
(JOIN STOCK COMPANY «SIBERIAN GROUP OF CHEMICAL ENTERPRISES»)
-
17:30
SELECTION OF CARRIER SALT FOR MOLTEN SALT FAST REACTOR
-
Andrey Lizin
(Russian Federation)
-
17:30
Examination of ChS-68 Steel Used as a BN-600 Reactor Cladding Material
-
Natalia Glushkova
(Joint Stock Company «Institute of Nuclear Materials»)
-
17:30
X-RAY DIFFRACTION STRUCTURAL ANALYSIS OF STRUCTURAL AND FUEL MATERIALS FOR BN-600 REACTOR
-
Vladimir Tsygvintsev
(Joint Stock Company “Institute of Nuclear Materials”)
-
17:30
Study on the limits of confinement leakage rates of pool-type sodium-cooled fast reactor
-
FENGLONG WANG
(CHINA INSTITUTE OF ATOMIC ENERGY,BEIJING,CHINA)
-
17:30
(U,Pu)O2-x MOX pellet for Astrid reactor project
-
Thierry GERVAIS
(AREVA)
-
17:30
The Commercial Potential of the Dual-Component Nuclear Power System
-
Mikhail Baryshnikov
(Head of Back-End Departement)
-
17:30
Complex discussion of inherent safety fast reactors start-up with enriched uranium concept (strategical, economical aspects, problems of neutron physics etc.). R&D program proposal
-
Michael Orlov
(Private institution «Innovation and technology center for the «PRORYV» project»)
-
17:30
Thermal conductivity of non-stoichiometric (Pu0.928Am0.072)O2-x
-
Taku Matsumoto
(Japan Atomic Energy Agency)
-
17:30
A Conceptual design of engineering-scale plant applied the simplified MA-bearing fuel fabrication process
-
YOSHIKAZU YAMADA
(Japan Atomic Energy Agency)
-
17:30
Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow
-
Konstantin Mikityuk
(Paul Scherrer Institut)
-
17:30
Testing and Qualification of shielded flasks for handling sodium wetted large sized components of PFBR
-
Rajan Babu Vinayagamoothy
(BHAVINI, Dept of Atomic Energy, Kalpakkam)
-
17:30
CHALLENGES DURING CONSTRUCTION OF SODIUM PIPING SYSTEMS FOR 500MWe PROTOTYPE FAST BREEDER REACTOR
-
Rajan Babu Vinayagamoorthy
(Director (Technical))
-
17:30
The method of calculating tritium content in various technological media of BN-type reactors
-
Mikhail Kriachko
(Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering named after A. I. Leypunsky")
-
17:30
ESFR-SMART: new Horizon-2020 project on SFR safety
-
Konstantin Mikityuk
(Paul Scherrer Institut)
-
17:30
POSTREACTOR STATE OF THE STANDARD AND EXPERIMENTAL BN-600 FUEL KINDS
-
Evgenii Kinev
(Institute of Nuclear Materials)
-
17:30
Benchmark Between EDF And IPPE On The Behavior Of Low Sodium Void Reactivity Effect Sodium Fast Reactor During An Unprotected Loss Of Flow Accident
-
David Lemasson
(EDF)
-
17:30
Fabrication process of NpO2 pellets
-
Bangyue YIN
(CIAE)
-
17:30
The behavior features of fuel elements with nitride fuel - theory and experiment
-
Igor Konovalov
(National Research Nuclear University "MEPhI")
-
17:30
The core of the LFR-AS-200: robustness for safety
-
Giacomo Grasso
(Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA))
-
17:30
Mechanical Design Evaluation of Fuel Assembly for PGSFR
-
Kyungho Yoon
(Korea Atomic Energy Research Institute)
-
17:30
Design and Development of Stroke Limiting Device for Control & Safety Rod Drive Mechanisms (CSRDMs) of future FBRs
-
RAGHUPATHY S.
(Indira Gandhi Centre for Atomic Research, Kalpakkam)
-
17:30
Main outcomes from the JASMIN project: development of ASTEC-Na for severe accident simulation in Na cooled fast reactors
-
NATHALIE GIRAULT
(IRSN)
-
17:30
Passive Shutdown Systems for Liquid Metal-Cooled Fast Reactors
-
Staffan Qvist
(LeadCold AB)
-
17:30
Assessment of accuracy from the use of point kinetics when analyzing transition processes in high power fast reactor
-
Igor Suslov
(ITC "PRORYV" Project)
-
17:30
Overview of the U.S. DOE fast reactor fuel development program
-
William Carmack
(Idaho National Laboratory)
-
17:30
Development of the U.S. Sodium Component Reliability Database
-
Matthew Denman
(Sandia National Laboratories)
-
17:30
Code Qualification Plan for an Advanced Austenitic Stainless Steel, Alloy 709, for Sodium Fast Reactor Structural Applications
-
Krishnamurti Natesan
(Argonne National Laboratory)
-
17:30
Controlling FCCI with Pd in metallic fuel
-
Michael Benson
(Idaho National Laboratory)
-
17:30
Probabilistic Safety Analysis of NPP with BREST-OD-300 reactor
-
Mikhail Ivochkin
(JSC NIKIET, MOSCOW/RUSSIA)
-
17:30
INSERTION RELIABILITY STUDIES FOR THE RBC-TYPE CONTROL RODS IN ASTRID
-
Denis Lorenzo
(CEA)
-
17:30
Synergetic mechanism of high temperature radiation embrittlement of austenitic steels under long term neutron irradiation at high temperatures
-
Victoria Shvetsova
(Central Research Institute of Structural Materials “Prometey”)
-
17:30
EVALUATION OF COBALT FREE COATINGS AS HARDFACING MATERIAL CANDIDATES IN SODIUM FAST REACTOR
-
FABIEN ROUILLARD
(CEA)
-
17:30
Passive Complementary Safety Devices for ASTRID severe accident prevention
-
Edouard Bissen
(CEA)
-
17:30
On-site nuclear fuel cycle of “BREST” reactors
-
Andrei Glazov
(Institution “Innovation and Technology Center by “PRORYV” Project”, State Atomic Energy Corporation “Rosatom”)
-
17:30
BISON for Metallic Fuels Modeling
-
Christopher Matthews
(Los Alamos National Laboratory)
-
17:30
IMPLEMENTATION STATUS OF CONTAIN-LMR SODIUM CHEMISTRY MODELS INTO MELCOR 2.1
-
David Louie
(Sandia National Laboratories)
-
17:30
OSCAR-Na validation against sodium loop experiments
-
Jean-Baptiste GENIN
(CEA, DEN)
-
17:30
A Demand Driven Way of Thinking Nuclear Development – Neutron Physical Feasibility of a Reactor Directly Operating SNF from LWR
-
Bruno Merk
(University of Liverpool)
-
17:30
On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors
-
Boris Hombourger
(Paul Scherrer Institut (PSI), Switzerland; École Polytechnique Fédérale de Lausanne (EPFL), Switzerland)
-
17:30
Development of Fast Reactors in the USSR and the Russian Federation; Malfunctions and Incidents in the Course of their Operation and Solution of Problems.
-
Lev Kochetkov
(Alexeevich)
-
17:30
Assessment of the reactivity effects of Gas cooled Fast Reactor
-
Jakub Lüley
(Slovak University of Technology)
-
17:30
FACILITY FOR ADVANCED FUELS THROUGH THE SOL-GEL METHOD
-
Balija Sreenivasulu
(IGCAR)
-
17:30
CHALLENGES IN THE FABRICATION AND RECYCLING OF MIXED CARBIDE FUEL
-
SUDHIR MISHRA
(BHABHA ATOMIC RESEARCH CENTRE, INDIA)
-
17:30
Investigation of steel corrosion products mass transfer in sodium
-
Viktor Alekseev
(JSC "SSC RF-IPPE")
-
17:30
The influence of porosity on thermal conductivity of low-density uranium oxide.
-
Kyoichi Morimoto
(Japan Atomic Energy Agency)
-
17:30
Mechanical and Thermal Properties of (U,Pu)O2-x
-
Shun Hirooka
(Japan Atomic Energy Agency)
-
17:30
Evaluation of irradiation-induced point defects migration during neutron irradiation in modified 316 stainless steel
-
Yoshihiro Sekio
(Japan Atomic Energy Agency)
-
17:30
Remote detection of raised radioactivity in emission from Beloyarsk nuclear power plant
-
Gennady Kolotkov
(V.E. Zuev Institute of Atmospheric Optics SB RAS)
-
17:30
Extending the grid plate life - Incorporation of lower axial shield for FBTR
-
Sureshkumar KV
(RFG, IGCAR)
-
17:30
APPLICATION OF PHYSICAL MODELING WHEN CALIBRATING HIGH RANGE ELECTROMAGNETIC FLOWMETERS
-
Vadim Alexandrovich Shurupov
(JSC “SSC RF – IPPE”)
-
17:30
DECAY HEAT REMOVAL SYSTEM IN THE SECONDARY CIRCUIT OF THE SODIUM-COOLED FAST REACTOR AND EVALUATION OF ITS CAPACITY
-
Iurii Ashurko
(IPPE)
-
17:30
Structural Design and Evaluation of a Steam Generator in PGSFR
-
Chang-Gyu PARK
(Korea Atomic Energy Research Institute)
-
17:30
VOIDING OF ELSY PRIMARY SYSTEM DURING STEAM GENERATOR LEAKAGE
-
Marti Jeltsov
(KTH Royal Institute of Technology)
-
17:30
Modeling of Lanthanide Transport in Metallic Fuels: Recent Progresses
-
Cetin Unal
(LANL)
-
17:30
Mathematical modeling of the mononitride nuclear fuel production processes
-
Igor Peshkichev
(RFNC-VNIITF)
-
17:30
The study of U-232 accumulation in reprocessed uranium for fast reactor fuel cycle
-
Mikhail Kriachko
(Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering named after A. I. Leypunsky")
-
17:30
Thermal and elastic properties of CexTh1-xO2 mixed oxides: a self-consistent thermodynamic approach
-
Anton Filanovich
(Ural Federal University)
-
17:30
CORROSION OF 12X18H10T STEEL IN Ce-, Nd- AND U-CONTAINING MOLTEN LiCl-KCl EUTECTIC
-
Evgeniya Nikitina
(Institute of High Temperature Electrochemistry)
-
17:30
ELECTRICAL CONDUCTIVITY OF MOLTEN LiCl-KCl EUTECTIC WITH COMPONENTS OF SPENT NUCLEAR FUEL
-
Alexander Salyulev
(Institute of High Temperature Electrochemistry)
-
17:30
Change in Mechanical Properties of Spent Fast Reactor Claddings
-
Svetlana Barsanova
(Joint Stock Company «Institute of Nuclear Materials»)
-
17:30
STATISTICAL INVESTIGATION OF RADIATION-INDUCED POROSITY IN BN FUEL CLADDINGS USING SCANNING ELECTRON MICROSCOPY
-
Vladimir Pastukhov
(Joint Stock Company "Institute of Nuclear Materials")
-
17:30
An Assessment of Fission Product Scrubbing in Sodium Pools Following a Core Damage Event in a Sodium Cooled Fast Reactor
-
Matthew Bucknor
(Argonne National Laboratory)
-
17:30
The Computer model for the economic assessment of NPP pilot demonstration energy complex with BREST-OD-300 reactor (REM Proryv Project)
-
Nikolay Molokanov
(ROSATOM, JSC “NIKIET”, MEPhI)
-
17:30
CFD Simulation of Corium / Materials Interaction for Severe Accidents
-
Stéphane BEILS
(AREVA NP)
-
17:30
Development of Ultra Sub-size Tensile Specimen for Evaluation of Tensile Properties of Irradiated Materials
-
Puthiyavinayagam Pillai
(Indira Gandhi Centre for Atomic Research)
-
17:30
Preliminary Safety Performance Assessment of ESFR CONF-2 Sphere-pac‐Fueled Core
-
Sara Bortot
(KTH)
-
17:30
Application of Heterogeneous Fuel Assemblies in the Core of Modular Fast Sodium Reactor
-
Yaroslav Kotov
(National Recearch Centre "Kurchatov Institute")
-
17:30
Improving inherent safety BN-800 by the use of fuel assembly with (U, Pu)C microfuel.
-
Nikolay Maslov
(National Research Centre "Kurchatov Institute" National Research Nuclear University MEPhI (Moscow Engineering Physics Institute))
-
17:30
Key features of design, manufacturing and implementation of laboratory and industrial equipment for Mixed Uranium – Plutonium Oxide (MOX) and Nitride fuel pellets fabrication in Russia
-
Alexander Denisov
(Deputy Director International Business Sosny R&D Company)
Vincent Reynaud
(CHAMPALLE SAS)
-
17:30
Feasibility of MA Transmutation by (MA, Zr)Hx in Radial Blanket Region of Fast Reactor and Plan of Technology Development
-
Kazumi IKEDA
(Mitsubishi FBR Systems, Inc.)
-
17:30
Towards a new approach for structural materials of Lead Fast Reactors
-
Pietro Agostini
(ENEA)
-
17:30
The optimization of core characteristics of fast molten salt reactor based on neutron-physical and thermal-hydraulic calculations and the analysis of fuel cycle closure options
-
Mikhail Belonogov
(RFNC-VNIITF named after academ. E.I. Zababakhin)
-
17:30
Impact of the irradiation of an ASTRID-type core during an ULOF with SIMMER-III
-
Sandra POUMEROULY
(EDF R&D)
-
17:30
Tradeoff Study of Advanced Transmutation Fuels in Sodium-cooled Fast Reactors
-
Nicolas Stauff
(Argonne National Laboratory)
-
17:30
High temperature design and evaluation of forced draft sodium-to-air heat exchanger in PGSFR
-
Nak Hyun Kim
(Korea Atomic Energy Reasearch Institute)
-
17:30
Thermal Annealing Effect on Recovery of Corrosion Properties of EP-450 Steel Irradiated IN BN-600 Reactor to High Damage Doses
-
Oleg Golosov
(Joint Stock Company "Institute of Nuclear Materials")
-
17:30
Investigation of Radiation-Induced Swelling of EK-164 Steel, an Advanced Material for BN-600 and BN-800 Claddings
-
Irina Portnykh
(Joint Stock Company "Institute of Nuclear Materials")
-
17:30
Sodium compatibility of Recently-Developed Optimized Grade 92 and its Weldments for Advanced Fast Reactors
-
Meimei Li
(Argonne National Lab)
-
17:30
FEATURES OF THE NUCLEAR FUEL CYCLE SYSTEMS BASED ON JOINT OPERATION OF FAST AND THERMAL REACTORS
-
Victor Dekusar
(Dekusar)
