• DocumentCode
    1542410
  • Title

    A study on the sensitivity of self-powered neutron detectors (SPNDs)

  • Author

    Lee, Wanno ; Cho, Gyuseong ; Kim, Kwanghyun ; Kim, Hee Joon ; Choi, Yuseon ; Park, Moon Ghu ; Kim, Soongpyung

  • Author_Institution
    Dept. of Nucl. Eng., Korea Adv. Inst. of Sci. & Technol., Taejon, South Korea
  • Volume
    48
  • Issue
    4
  • fYear
    2001
  • fDate
    8/1/2001 12:00:00 AM
  • Firstpage
    1587
  • Lastpage
    1591
  • Abstract
    Self-powered neutron detectors (SPNDs) are widely used in reactors to monitor neutron flux, while they have several advantages such as small size, and relatively simple electronics required in conjunction with those usages, they have some intrinsic problems of the low level of output current-a slow response time and the rapid change of sensitivity-that make it difficult to use for a long term. Monte Carlo simulation was used to calculate the escape probability as a function of the birth position of emitted beta particle for geometry of rhodium-based SPNDs. A simple numerical method calculated the initial generation rate of beta particles and the change of generation rate due to rhodium burnup. Using results of the simulation and the simple numerical method, the burnup profile of rhodium number density and the neutron sensitivity were calculated as a function of burnup time in reactors. This method was verified by the comparison of this and other papers, and data of YGN3.4 (Young Gwang Nuclear plant 3, 4) about the initial sensitivity. In addition, for improvement of some properties of rhodium-based SPNDs, which are currently used, a modified geometry is proposed. The proposed geometry, which is tube-type, is able to increase the initial sensitivity due to increase of the escape probability. The escape probability was calculated by changing the thickness of the insulator and compared solid-type with tube-type about each insulator thickness. The method used here can be applied to the analysis and design of other types of SPNDs
  • Keywords
    Monte Carlo methods; fission reactor instrumentation; rhodium; self-powered neutron detectors; Monte Carlo simulation; Rh; emitted beta particle; escape probability; initial generation rate; neutron sensitivity; rhodium burnup; self-powered neutron detectors; Absorption; Beta rays; Biomedical engineering; Detectors; Dielectrics and electrical insulation; Inductors; Information geometry; Neutrons; Power engineering and energy; Probability;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9499
  • Type

    jour

  • DOI
    10.1109/23.958400
  • Filename
    958400