• DocumentCode
    1079555
  • Title

    Evaluation of Lithium Gadolinium Borate Capture-Gated Spectrometer Neutron Efficiencies

  • Author

    Menaa, Nabil ; Villani, Marcel ; Croft, Stephen ; McElroy, Robert B. ; Philips, Sasha A. ; Czirr, J. Bart

  • Author_Institution
    Canberra (An AREVA Co.), Meriden, CT
  • Volume
    56
  • Issue
    3
  • fYear
    2009
  • fDate
    6/1/2009 12:00:00 AM
  • Firstpage
    911
  • Lastpage
    914
  • Abstract
    Accurate determination of neutron dose equivalent requires knowledge of the neutron energy distribution. Existing neutron spectrometers, such as Bonner sphere sets, are typically bulky and require long acquisition times. Hence, a handheld or portable system that could perform area monitoring with acceptable accuracy would be of interest. Such a device will require a detector that is efficient, and possesses gamma-neutron discrimination capabilities. An organic scintillator that contains lithium, gadolinium, and boron, all three of which possess isotopes with large neutron capture cross-sections for highly exothermic reactions, has been recently developed by MSI/Photogenics. This combination of materials provides for the detection of fast neutrons by proton recoil which when used in conjunction with a slow neutron capture gate allows total energy information to be obtained. The system also responds to gamma-rays but n-gamma discrimination techniques allow it to be applied in mixed fields. Photogenics recently completed the full demonstration of a Lithium Gadolinium Borate (LGB) neutron spectrometer\´s performance under a Department of Homeland Security Domestic Nuclear Detection Office (DNDO) grant. A potential application suggested for this technology is in the identification of shielded fissile materials. A 2" times 2" (50.8 mm times 50.8 mm) sample of composite scintillator, consisting of lithium gadolinium borate crystals in a plastic scintillator matrix, produced by Photogenics has been tested for this purpose. The Tests consist of verifying the n-gamma discrimination and measurements of both capture and capture gated efficiencies using 252Cf and Am-Li neutron sources of various activities under a variety of gamma shielding and neutron attenuation geometries. The results, for this small test sample, showed that in addition to its rudimentary spectroscopic capability, the Photogenics LGB detector has a overall neutron detection efficiency that is attra- ctive for handheld applications.
  • Keywords
    gamma-ray apparatus; gamma-ray detection; neutron detection; neutron sources; neutron spectrometers; position sensitive particle detectors; solid scintillation detectors; 252Cf neutron sources; Am-Li neutron sources; Bonner sphere sets; MSI/Photogenics; exothermic reactions; gamma shielding; gamma-neutron discrimination; lithium gadolinium borate capture-gated neutron spectrometer; neutron attenuation; neutron capture cross-sections; neutron detection efficiency; neutron dose equivalent; neutron energy distribution; plastic scintillator matrix; proton recoil; shielded fissile materials; size 2 in; Boron; Gamma ray detection; Gamma ray detectors; Isotopes; Lithium compounds; Monitoring; Neutrons; Protons; Spectroscopy; Testing; Dose; LGB; neutron; scintillator; spectroscopy;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9499
  • Type

    jour

  • DOI
    10.1109/TNS.2009.2015299
  • Filename
    5076057