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
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