• DocumentCode
    2718942
  • Title

    Development and validation of the automatic control rods operation system for ABWR

  • Author

    Miura, Hiroshi ; Arakawa, Akio

  • Author_Institution
    Dept. of Nucl. Control & Electr. Eng., Toshiba Corp., Yokohama, Japan
  • fYear
    1997
  • fDate
    8-13 Jun 1997
  • Firstpage
    42413
  • Lastpage
    42417
  • Abstract
    TOSHIBA has introduced the first automatic control rods operation system for the first ABWR (advanced BWR) in the world. The automatic control rods operation system, which is named APR (Automatic Power Regulator), has core critical approach control, pressurization control and power control function and covers the operation from reactor startup to about 70% electrical power. APR calculates the manipulating demand of control rods from feedback signals, that are neutron flux, calculated temperature rise ratio and electrical power. The manipulating demand of control rods is dispatched to an RC&IS (rod control and information system) as an insertion/withdrawal signal. The control rods to be operated are automatically selected by the RC&IS. In the development of this system, a 3D core simulator was adopted to verify the control algorithm and to validate this system. Prior to startup tests, a 3D core simulator was used to precisely predict dynamics and to verify control parameters. In parallel with the introduction of APR to ABWRs, operators were trained to operate the APR with a plant wise simulator, in which the 3D core simulator is adopted for precise simulation of flux behavior. Through this training, operators can obtain the skill to operate the APR system under normal plant condition and abnormal condition such as plant transients or APR failure
  • Keywords
    fission reactor core control; fission reactor instrumentation; fission reactor monitoring; nuclear engineering computing; nuclear power stations; power station control; 3D core simulator; Automatic Power Regulator; advanced BWR nuclear power plants; automatic control rods operation system; computer simulation; control algorithm; core critical approach control; insertion/withdrawal signal; operator training; power control function; pressurization control; rod control and information system; Automatic control; Control systems; Feedback; Inductors; Information systems; Neutrons; Power control; Pressure control; Regulators; Temperature control;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Human Factors and Power Plants, 1997. Global Perspectives of Human Factors in Power Generation., Proceedings of the 1997 IEEE Sixth Conference on
  • Conference_Location
    Orlando, FL
  • Print_ISBN
    0-7803-3769-7
  • Type

    conf

  • DOI
    10.1109/HFPP.1997.624807
  • Filename
    624807