• DocumentCode
    769597
  • Title

    Application of neutron imaging plate and neutron CT methods on nuclear fuels and materials

  • Author

    Yasuda, R. ; Matsubayashi, M. ; Nakata, M. ; Harada, K. ; Amano, H. ; Sasajima, F. ; Nishi, M. ; Horiguchi, Y.

  • Author_Institution
    Japan Atomic Energy Res. Inst., Kashiwa, Japan
  • Volume
    52
  • Issue
    1
  • fYear
    2005
  • Firstpage
    313
  • Lastpage
    316
  • Abstract
    Advanced neutron radiography techniques such as the neutron imaging plate (NIP) and neutron computed tomography (NCT) methods have been investigated in the practicability for the postirradiation examination (PIE). In current works, an unirradiated fuel rod was examined by NIP and NCT methods in order to collect the fundamental data for applying these techniques to the PIE. A fuel rod used is composed of seven-enriched UO2 and two-natural UO2 pellets with controlled sizes and shape that are loaded into a Zircaloy tube. The neutron radiography tests were performed by NIP and NCT methods at the 2nd Thermal Neutron Radiography Facility (TNRF-2) in the Japan Research Reactor (JRR)-3. In the NIP image of the fuel rod, the difference in the size, shape, and enrichment between the UO2 pellets is obviously recognized. In the case of NCT method, the images clearly show the detailed shape of the cross section in both enriched and natural pellets; and difference in the enrichment between those pellets is also observed. In addition, size difference between fuel parts of specifications and those in NCT images is evaluated.
  • Keywords
    computerised tomography; fission reactor fuel; fission research reactors; neutron effects; neutron radiography; uranium compounds; Japan Research Reactor; Thermal Neutron Radiography Faculty; UO2; Zircaloy tube; advanced neutron radiography techniques; cross section shape; neutron computed tomography methods; neutron imaging plate; nuclear fuels; nuclear materials; postirradiation examination; seven-enriched UO2; size evaluation; two-natural UO2 pellets; unirradiated fuel rod; Computed tomography; Image recognition; Inductors; Neutrons; Nuclear fuels; Performance evaluation; Radiography; Shape control; Size control; Testing; Computed tomography; imaging plate; neutron radiography; nuclear fuels; size evaluation;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9499
  • Type

    jour

  • DOI
    10.1109/TNS.2005.844297
  • Filename
    1417156