• DocumentCode
    2112673
  • Title

    Safety Analysis for IPWR under Over-Pressurizing Accident Conditions

  • Author

    Dai Shoubao ; Peng Minjun

  • Author_Institution
    Coll. of Nucl. Sci. & Technol., Harbin Eng. Univ., Harbin, China
  • fYear
    2010
  • fDate
    28-31 March 2010
  • Firstpage
    1
  • Lastpage
    5
  • Abstract
    In this paper an integral pressurized water reactor (IPWR) has 100 MW capacity with passive safety features. The design of IPWR focuses on enhancing the safety and reliability of the reactor by employing inherent safety features such as low core power density, elimination of large break loss of coolant accident, etc. In addition, in order to prevent the progression of emergency situations into accident, IPWR is provided with a number of engineered safety features such as passive residual heat removal system (PRHRS).This paper presents an overview of the IPWR design, and results of over-pressure accident analyses. The results of the accident analyses show that IPWR provides the inherent over-pressure protection capability for design basis accidents without actuation of any protection devices such as safety valves, rupture disks, etc.
  • Keywords
    fission reactor cooling; fission reactor safety; light water reactors; power generation protection; power generation reliability; IPWR; integral pressurized water reactor; over-pressurizing accident conditions; passive residual heat removal system; power 100 MW; safety analysis; Accidents; Coolants; Design engineering; Heat engines; Inductors; Power engineering and energy; Protection; Reliability engineering; Safety devices; Valves;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Power and Energy Engineering Conference (APPEEC), 2010 Asia-Pacific
  • Conference_Location
    Chengdu
  • Print_ISBN
    978-1-4244-4812-8
  • Electronic_ISBN
    978-1-4244-4813-5
  • Type

    conf

  • DOI
    10.1109/APPEEC.2010.5449208
  • Filename
    5449208