• DocumentCode
    1341678
  • Title

    Neutron Dosimetry and 3-D Neutron Transport Calculations as Toolkit at HFR Petten for Detailed Neutron Monitoring and Damage Analysis

  • Author

    Mutnuru, Ravi Kiran ; Ketema, Dik J. ; Van der Marck, Steven C.

  • Author_Institution
    Nucl. Res. & consultancy Group (NRG), Petten, Netherlands
  • Volume
    57
  • Issue
    6
  • fYear
    2010
  • Firstpage
    3683
  • Lastpage
    3686
  • Abstract
    Dosimetry at the High Flux Reactor in Petten, the Netherlands, serves a variety of purposes ranging from demonstrating compliance with the license for operating the reactor to validating the predictions of displacements per atom (DPA) in material irradiations. It is also used in the validation of the 3-D neutron transport calculations during post-irradiation analysis to normalize the spectrum obtained from these calculations. In this paper, a thorough examination of irradiated steel specimens is carried out using the measurements performed with the neutron activation technique as well as the 3-D neutron transport calculations to check the consistency in the resulting DPA values.
  • Keywords
    dosimetry; fission research reactors; neutrons; 3D neutron transport calculation; HFR Petten; High Flux Reactor; Netherlands; damage analysis; neutron dosimetry; neutron monitoring; Dosimetry; Monitoring; Monte Carlo methods; Neutrons; Radiation effects; Activation foils; Monte Carlo N-Particle Transport Code (MCNP); displacements per atom (DPA); material damage; neutron dosimetry;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9499
  • Type

    jour

  • DOI
    10.1109/TNS.2010.2075940
  • Filename
    5593908