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2020年第二届能源、动力、环境与计算机应用国际学术会议(ICEPECA2020)
中国 • 北京市   2020年11月22日-2020年11月23日
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  • 主题报告
主题报告
  • 报告题目:Application of New Perspective Materials as Advanced Tolerant Fuel Cladding Materials in Nuclear Reactors of Future Generation
  • 报告摘要:
    Currently, the comprehension among the specialists and functionaries throughout the world is getting stronger that the nuclear industry can encounter serious difficulties in development in the case of insufficiently decisive measures to enhance the safety level of nuclear objects and to ensure clean energy and green world. The keen competition with renewable energy sources like wind, solar or geothermal energy takes place presently and is expected to continue in future decades. One of main measures of nuclear safety enhancement could be a drastic renovation of materials used in nuclear industry. The analytical models of high-temperature oxidation of new perspective materials including chromium-nickel-based alloys, zirconium-based cladding with protective chromium coating, FeCrAl alloys and composite claddings on the basis of SiC/SiC in the course of design-basis and beyond-design-basis accidents at nuclear power plants (NPPs) are developed and implemented to severe accident computer running code. The comparison with available experimental data is conducted. The preliminary calculations of nuclear pressurized water reactor loss-of-coolant accidents with new types of claddings demonstrate encouraging results for hydrogen generation rate and integral hydrogen production. It looks optimistic for considerable upgrade of safety level for future generation NPPs using new fuel and cladding materials.
  • 报告人:Prof. Alexander Vasiliev
  • 报告人单位:Moscow Institute of Physics and Technology, Russia
  • 个人介绍:
    In 1985 Alexander Vasiliev finished Moscow Institute of Physics and Technology (diploma cum laudis). From November 1985 to November 1988 he attended postgraduate courses attached to I.V.Kurchatov Atomic Energy Institute, Moscow. In March 1989 Alexander Vasiliev defended the Ph.D. entitled, "Models of Thermal Processes under the Action of the Moderate Energy Fluxes on Materials". Principal advisor - Prof. L.A.Bolshov, currently Head of Nuclear Safety Institute, Moscow, Academician of Russian Academy of Sciences. From 1988 to 1997 Alexander Vasiliev worked at I.V.Kurchatov Atomic Energy Institute, Moscow. Field of occupation: development and verification of Russian reference “best estimate” computer code SOCRAT on water-water nuclear reactor (VVER) and liquid metal fast reactor (LMFR) accident application; development and verification of Russian new generation sub-channel thermal-hydraulic and neutronic code HYDRA, application of code SOCRAT to normal operation, design-basis-accidents & beyond-design-basis-accidents at nuclear power plants, including fission products release and transport in containment and atmosphere, and spent fuel pool accidents. In 1994 he worked as research associate in Department of Nuclear Engineering, University of Tennessee, Knoxville, US. He performed investigation work on theoretical establishment of critical heat flux and thermal limit values under the conditions of natural low-mass low-pressure two-phase flow following reactor accident. From 1997 to present time Dr. Alexander Vasiliev works at Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE) as senior research associate, head of laboratory, principal research associate. The main areas of interest include analysis of accidents at nuclear power plants (mainly Russian VVER type), radioactive waste operation, application and behavior of new materials in nuclear energy including oxidation of zirconium-based and new perspective accident-tolerant fuel claddings in steam-oxygen-nitrogen gas mixtures.
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