• DocumentCode
    817023
  • Title

    The PWR Protection System - Present and Future

  • Author

    von Haebler, D. ; Meijer, C.H.

  • Author_Institution
    Instrumentation and Control Kraftwerk Union Erlangen, West Germany
  • Volume
    22
  • Issue
    1
  • fYear
    1975
  • Firstpage
    784
  • Lastpage
    797
  • Abstract
    In a nuclear power generating station, the system used to protect the reactor and its containment is the plant protection sytem. The pressurized-water-reactor (PWR) protection systems encompass all electrical and mechanical devices and circuitry (from sensors to actuated device input terminals) involved in generating those signals associated with the protective function. These signals include actuation signals for the Reactor Protection System (RPS) and Engineered Safety Features System (ESFS) such as Safety Injection Actuation System, Containment Spray Actuation System, Main Steam Isolation System, Auxiliary Feedwater Actuation System, and Recirculation Actuation System. This paper deals with the present status and future development of the Plant Protection Systems utilized by Combustion Engineering, Inc. (C-E) and Kraftwerk Union (KWU) for their Pressurized Water Reactors. The latest techniques of signal processing, logic design, reactor trip and engineered safety features actuation circuitry, automatic testing, isolation and interfacing, are discussed. Current system design criteria, which as a result of the dynamic national and international licensing atmospheres influence system design philosophies, are highlighted.
  • Keywords
    Circuits; Inductors; Mechanical sensors; Nuclear power generation; Power generation; Power system protection; Safety; Sensor systems; Signal generators; Systems engineering and theory;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9499
  • Type

    jour

  • DOI
    10.1109/TNS.1975.4327746
  • Filename
    4327746