Design of a High-Speed Neutron Imager Using a Boron-Loaded Organic Glass Scintillator

Upgrades to the Spallation Neutron Source at Oak Ridge National Laboratory will provide a second target station and an increased neutron flux, which will offer a more powerful tool for neutron reflectometry. To fully utilize the higher neutron flux, a high-speed, neutron-imaging device (an imaging p...

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Bibliographic Details
Published inIEEE transactions on nuclear science Vol. 69; no. 6; pp. 1317 - 1321
Main Authors Johnson, Erik B., van Loef, Edgar, Kaffine, Meghan, Sosa, Charles
Format Journal Article
LanguageEnglish
Published New York IEEE 01.06.2022
The Institute of Electrical and Electronics Engineers, Inc. (IEEE)
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Summary:Upgrades to the Spallation Neutron Source at Oak Ridge National Laboratory will provide a second target station and an increased neutron flux, which will offer a more powerful tool for neutron reflectometry. To fully utilize the higher neutron flux, a high-speed, neutron-imaging device (an imaging plane) specifically for reflectometry is required. The neutron imaging plane requires a detection efficiency of 60% for 2 Å neutrons for event rates exceeding 2 Mcps/cm 2 with less than 10% dead time. A novel organic glass scintillator material loaded with a boron compound demonstrated good neutron sensitivity. Simulations show that the detection efficiency for thermal neutrons can reach 60% with a 500-<inline-formula> <tex-math notation="LaTeX">\mu \text{m} </tex-math></inline-formula> thickness, if the glass is loaded with 99% enriched <inline-formula> <tex-math notation="LaTeX">^{10}\text{B} </tex-math></inline-formula> compound at 10% wt. A lower concentration of 95% enrichment at 5% wt loading can provide 60% efficiency with a thickness slightly above 1 mm. The decay time of the scintillator is less than 100 ns, providing a fast response for high rate counting. The instrument design is based on detecting the neutron with a fast scintillation material and integrating silicon photomultipliers (SiPMs) with high-speed digital electronics. Traditional pulse sampling using a high-speed analog to digital converter (ADC) to conduct pulse shape discrimination is not viable for imaging, and a new technique has been formulated for this material using a time over threshold (TOT) method to isolate neutrons from gamma-ray interactions. The gamma-neutron peak separation is greater than two sigma, and with a thin scintillator, the gamma-ray rejection per detected neutron should meet the design specification of <inline-formula> <tex-math notation="LaTeX">10^{-6} </tex-math></inline-formula>. Using the TOT method, the digital information to be processed by an interfacing ADC is reduced allowing for readout per SiPM, providing a position resolution close to 1 mm.
Bibliography:USDOE Office of Science (SC)
SC0020610
ISSN:0018-9499
1558-1578
DOI:10.1109/TNS.2021.3130491