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
Link To Document :
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