• DocumentCode
    1586585
  • Title

    Numerical simulation and safety analysis on flow field of a 1000 MW unit nuclear reactor pressure vessel

  • Author

    Liu, Jian-quan ; Hu, Yong-sheng ; Sun, Bao-min ; Bai, Tao

  • Author_Institution
    Key Laboratory of Condition Monitoring and Control for Power Plant Equipment, North China Electric Power University, Beijing, China
  • fYear
    2012
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    The flow field of a 1000 MW unit nuclear reactor pressure vessel operation process was numerically studied with realizable k-ε model. the reactor normal operating, circuit fault and isolation layer being plug conditions were studied. The different reactor flow characteristics between normal operating and two fault conditions were compared. The numerical simulation results show as follows, The core inlet flow distribution is certain heterogeneity during normal operation, flow velocity are fast in the core inlet middle and surrounding area, The core inlet annular channel blocking zone has a certain regulation to the flow distribution, Increasing flow resistance coefficient, Core inlet flow is more evenly; in circuit fault condition, Other loop currents can add flow to the loop; reduce flow resistance coefficient, Core inlet flow is more evenly, too large resistance coefficient can enlarge heterogeneity flow distribution, The numerical simulation results provide a theoretical basis to judge flow field when circuit fault and isolation layer being plug conditions,it can also provide some theoretical basis for the nuclear reactor pressure vessel operation.
  • Keywords
    circuit fault; circuit isolation layer; flow field; numerical simulation; realizable k-ε model;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    World Automation Congress (WAC), 2012
  • Conference_Location
    Puerto Vallarta, Mexico
  • ISSN
    2154-4824
  • Print_ISBN
    978-1-4673-4497-5
  • Type

    conf

  • Filename
    6321529