Neutron Detection and Multiplicity Counting Using a Boron-loaded Plastic Scintillator/bismuth Germanate Phoswich Detector Array

Neutron Detection and Multiplicity Counting Using a Boron-loaded Plastic Scintillator/bismuth Germanate Phoswich Detector Array
Title Neutron Detection and Multiplicity Counting Using a Boron-loaded Plastic Scintillator/bismuth Germanate Phoswich Detector Array PDF eBook
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Pages
Release 2006
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ISBN

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Neutron detection and multiplicity counting has been investigated using a boron-loaded plastic scintillator/bismuth germanate phoswich detector array. Boron-loaded plastic combines neutron moderation (H) and detection ([sup 10]B) at the molecular level, thereby physically coupling increasing detection efficiency and decreasing die-away time with detector volume. Both of these characteristics address a fundamental limitation of thermal-neutron multiplicity counters, where [sup 3]He proportional counters are embedded in a polyethylene matrix. Separation of the phoswich response into its plastic scintillator and bismuth germanate components was accomplished on a pulse-by-pulse basis using custom integrator and timing circuits. In addition, a custom time-tag module was used to provide a time for each detector event. Analysis of the combined energy and time event stream was performed by calibrating each detector's response and filtering based on the presence of a simultaneous energy deposition corresponding to the [sup 10]B(n, alpha) reaction products in the plastic scintillator (93 keV[sub ee]) and the accompanying neutron-capture gamma ray in the bismuth germanate (478 keV). Time-correlation analysis was subsequently performed on the filtered event stream to obtain shift-register-type singles and doubles count rates. Proof-of-principle measurements were conducted with a variety of gamma-ray and neutron sources including [sup 137]Cs, [sup 54]Mn, AmLi, and [sup 252]Cf. Results of this study indicate that a neutron-capture probability of [approximately]10% and a die-away time of [approximately]10 [micro]s are possible with a 4-detector array with a detector volume of 1600 cm[sup 3]. Simulations were performed that indicate neutron-capture probabilities on the order of 50% and die-away times of less than 4 [micro]s are realistically achievable. While further study will be required for practical application of such a detection system, the results obtained in this investigation are encouraging and may lead to a new class of high-efficiency, short die-away time neutron multiplicity counters capable of extending current nondestructive assay methods for special nuclear materials.

Neutron Detection and Multiplicity Counting Using a Boron-loaded Plastic Scintillator/bismuth Germanate Phoswich Detector Array

Neutron Detection and Multiplicity Counting Using a Boron-loaded Plastic Scintillator/bismuth Germanate Phoswich Detector Array
Title Neutron Detection and Multiplicity Counting Using a Boron-loaded Plastic Scintillator/bismuth Germanate Phoswich Detector Array PDF eBook
Author Michael Conrad Miller
Publisher
Pages 364
Release 1997
Genre Neutron counters
ISBN

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Neutron Detection and Applications Using a BC454

Neutron Detection and Applications Using a BC454
Title Neutron Detection and Applications Using a BC454 PDF eBook
Author
Publisher
Pages 8
Release 1998
Genre
ISBN

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Neutron detection and multiplicity counting has been investigated using a boron-loaded plastic scintillator (BC454)/bismuth germanate (BGO) phoswich detector array. Boron-loaded plastic combines neutron moderation (H) and detection (1°B) at the molecular level, thereby physically coupling increasing detection efficiency and decreasing die-away time with detector volume. Separation of the phoswich response into its plastic scintillator and bismuth germanate components was accomplished on an event-by-event basis using custom integrator and timing circuits, enabling a prompt coincidence requirement between the BC454 and BGO to be used to identify neutron captures. In addition, a custom time-tag module was used to provide a time for each detector event. Time-correlation analysis was subsequently performed on the filtered event stream to obtain shift-register-type singles and doubles count rates.

2004 IEEE Nuclear Science Symposium Conference Record

2004 IEEE Nuclear Science Symposium Conference Record
Title 2004 IEEE Nuclear Science Symposium Conference Record PDF eBook
Author
Publisher
Pages 768
Release 2004
Genre Imaging systems in medicine
ISBN

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American Doctoral Dissertations

American Doctoral Dissertations
Title American Doctoral Dissertations PDF eBook
Author
Publisher
Pages 872
Release 1996
Genre Dissertation abstracts
ISBN

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Recent Developments in Neutron Detection and Multiplicity Counting with Liquid Scintillator

Recent Developments in Neutron Detection and Multiplicity Counting with Liquid Scintillator
Title Recent Developments in Neutron Detection and Multiplicity Counting with Liquid Scintillator PDF eBook
Author
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Pages 11
Release 2010
Genre
ISBN

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For many years at LLNL we have been developing time-correlated neutron detection techniques and algorithms for many applications including Arms Control, Threat Detection and Nuclear Material Assaying. Many of our techniques have been developed specifically for relatively low efficiency (a few %) inherent in the man-portable systems. Historically we used thermal neutron detectors (mainly 3He) taking advantage of the high thermal neutron interaction cross-sections but more recently we have been investigating fast neutron detection with liquid scintillators and inorganic crystals. We have discovered considerable detection advantages with fast neutron detection as the inherent nano-second production time-scales of fission and neutron induced fission are preserved instead of being lost in neutron thermalization required for thermal neutron detectors. We are now applying fast neutron technology (new fast and portable digital electronics as well as new faster and less hazardous scintillator formulations) to the safeguards regime and faster detector response times and neutron momentum sensitivity show promise in measuring, differentiating and assaying samples that have very high count rates as well as mixed fission sources (e.g. Cm and Pu). We report on measured results with our existing liquid scintillator array and progress on design of nuclear material assaying system that incorporates fast neutron detection.

Neutron Multiplicity Measurements with 3He Alternative

Neutron Multiplicity Measurements with 3He Alternative
Title Neutron Multiplicity Measurements with 3He Alternative PDF eBook
Author
Publisher
Pages 8
Release 2015
Genre
ISBN

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Counting neutrons emitted by special nuclear material (SNM) and differentiating them from the background neutrons of various origins is the most effective passive means of detecting SNM. Unfortunately, neutron detection, counting, and partitioning in a maritime environment are complex due to the presence of high-multiplicity spallation neutrons (commonly known as ''ship effect '') and to the complicated nature of the neutron scattering in that environment. A prototype neutron detector was built using 10B as the converter in a special form factor called ''straws'' that would address the above problems by looking into the details of multiplicity distributions of neutrons originating from a fissioning source. This paper describes the straw neutron multiplicity counter (NMC) and assesses the performance with those of a commercially available fission meter. The prototype straw neutron detector provides a large-area, efficient, lightweight, more granular (than fission meter) neutron-responsive detection surface (to facilitate imaging) to enhance the ease of application of fission meters. Presented here are the results of preliminary investigations, modeling, and engineering considerations leading to the construction of this prototype. This design is capable of multiplicity and Feynman variance measurements. This prototype may lead to a near-term solution to the crisis that has arisen from the global scarcity of 3He by offering a viable alternative to fission meters. This paper describes the work performed during a 2-year site-directed research and development (SDRD) project that incorporated straw detectors for neutron multiplicity counting. The NMC is a two-panel detector system. We used 10B (in the form of enriched boron carbide: 10B4C) for neutron detection instead of 3He. In the first year, the project worked with a panel of straw neutron detectors, investigated its characteristics, and developed a data acquisition (DAQ) system to collect neutron multiplicity information from spontaneous fission sources using a single panel consisting of 60 straws equally distributed over three rows in high-density polyethylenemoderator. In the following year, we developed the field-programmable gate array and associated DAQ software. This SDRD effort successfully produced a prototype NMC with*33% detection efficiency compared to a commercial fission meter.