• DocumentCode
    2929999
  • Title

    Valuation of power oscillations in a BWR after control rod banks withdrawal events

  • Author

    Costa, Antonella L. ; Pereira, Claubia ; da Silva, Clarysson A M ; Veloso, Maria Auxiliadora F

  • Author_Institution
    Dept. de Eng. Nucl., Univ. Fed. de Minas Gerais, Belo Horizonte, Brazil
  • fYear
    2009
  • fDate
    7-10 June 2009
  • Firstpage
    1
  • Lastpage
    6
  • Abstract
    The out-of-phase mode of oscillation is a very challenging type of instability occurring in BWR (Boiling Water Reactor) and its study is relevant because of the safety implications related to the capability to promptly detect any such inadvertent occurrence by in-core neutron detectors, thus triggering the necessary countermeasures in terms of selected rod insertion or even reactor shutdown. In this work, control rod banks withdrawal transient was considered to study the power instability occurring in a BWR. To simulate this transient, the control rod banks were continuously removed from the BWR core in different cases. The simulation resulted in a very large increase in the power. To perform the instability simulations, the RELAP5/MOD3.3 thermal hydraulic system code was coupled with the PARCS/2.4 3D neutron kinetic code. Data from a real BWR, the Peach Bottom, have been used as reference conditions and reactor parameters. The trend of the mass flow rate, pressure, coolant temperature and the void fraction to four thermal hydraulic channels symmetrically located in the core with respect to the core centre, were taken. The behavior of the thermal hydraulic parameters investigated presented out-of-phase evolution comparing the channels that represents each half of the core.
  • Keywords
    fission reactor cooling; fission reactor core control; fission reactor monitoring; fission reactor safety; light water reactors; neutron detection; BWR; PARCS/2.4 3D neutron kinetic code; Peach Bottom; RELAP5/MOD3.3 thermal hydraulic system code; boiling water reactor; control rod banks withdrawal events; control rod banks withdrawal transient; coolant temperature; fission reactor safety; in-core neutron detectors; mass flow rate; out-of-phase mode; power instability; power oscillations; pressure; thermal hydraulic channels; void fraction; Accidents; Coolants; Cost accounting; Discrete event simulation; Hydraulic systems; Inductors; Kinetic theory; Neutrons; Safety; Stability; BWR; PARCS; RELAP5; coupled codes;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2009 First International Conference on
  • Conference_Location
    Marseille
  • Print_ISBN
    978-1-4244-5207-1
  • Electronic_ISBN
    978-1-4244-5208-8
  • Type

    conf

  • DOI
    10.1109/ANIMMA.2009.5503687
  • Filename
    5503687