Journal
IEEE TRANSACTIONS ON NUCLEAR SCIENCE
Volume 69, Issue 6, Pages 1317-1321Publisher
IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC
DOI: 10.1109/TNS.2021.3130491
Keywords
Digital signal processing; neutron reflectometry (NR); organic glass scintillator (OGS); pulse shape discrimination (PSD)
Funding
- U.S. Department of Energy through the Phase I Small Business Innovative Research (SBIR) [DE-SC0020610]
- U.S. Department of Energy (DOE) [DE-SC0020610] Funding Source: U.S. Department of Energy (DOE)
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The upgrades to the Spallation Neutron Source will improve neutron reflectometry by providing a second target station and increased neutron flux. A high-speed neutron-imaging device is necessary to fully utilize the higher neutron flux. A novel scintillator material loaded with a boron compound has demonstrated good neutron sensitivity.
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 angstrom 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-mu m thickness, if the glass is loaded with 99% enriched 10B 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 10(-6). 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.
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