• DocumentCode
    2627841
  • Title

    Use of an LGB detector in nuclear nonproliferation applications

  • Author

    Flaska, Marek ; Pozzi, Sara A. ; Czirr, Bart

  • Author_Institution
    Department of Nuclear Engineering & Radiological Sciences, University of Michigan, 2928B Cooley Building, 2355 Bonisteel Boulevard, Ann Arbor, 48109-2104, USA
  • fYear
    2008
  • fDate
    19-25 Oct. 2008
  • Firstpage
    3376
  • Lastpage
    3380
  • Abstract
    Capture-gated detectors have attracted the attention of several researchers because of their promise for neutron spectroscopy in mixed neutron-gamma-ray fields. Examples are the boron-loaded detector (loaded with either natural B or B enriched in B-10), the Li-6-glass/plastic scintillation detector, and the lithium-gadolinium-borate (LGB) detector (loaded with Li-6, natural Gd, and B-10). In the work presented in this paper, the LGB plastic scintillation detector is investigated. This detector is sensitive to not only fast neutrons and gamma rays, but also to thermal neutrons. Some efforts have been made in the past to characterize this detector for several neutron and gamma-ray energies. In this paper, we compare measurements and Monte Carlo simulations for the LGB detector. In the comparisons, very good agreement is achieved, which indicates accurate Monte Carlo modeling. This work has applications in fields such as nuclear safeguards, nuclear nonproliferation, and national security.
  • Keywords
    Gamma ray detection; Gamma ray detectors; Gamma rays; Monte Carlo methods; National security; Neutrons; Plastics; Scintillation counters; Solid scintillation detectors; Spectroscopy;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Nuclear Science Symposium Conference Record, 2008. NSS '08. IEEE
  • Conference_Location
    Dresden, Germany
  • ISSN
    1095-7863
  • Print_ISBN
    978-1-4244-2714-7
  • Electronic_ISBN
    1095-7863
  • Type

    conf

  • DOI
    10.1109/NSSMIC.2008.4775066
  • Filename
    4775066