title: Monte Carlo simulation of a very high resolution thermal neutron detector composed of glass scintillator microfibers.
abstract: In order to develop a high spatial resolution (micron level) thermal neutron detector, a detector assembly composed of cerium doped lithium glass microfibers, each with a diameter of 1 μm, is proposed, where the neutron absorption location is reconstructed from the observed charged particle products that result from neutron absorption. To suppress the cross talk of the scintillation light, each scintillating fiber is surrounded by air-filled glass capillaries with the same diameter as the fiber. This pattern is repeated to form a bulk microfiber detector. On one end, the surface of the detector is painted with a thin optical reflector to increase the light collection efficiency at the other end. Then the scintillation light emitted by any neutron interaction is transmitted to one end, magnified, and recorded by an intensified CCD camera. A simulation based on the Geant4 toolkit was developed to model this detector. All the relevant physics processes including neutron interaction, scintillation, and optical boundary behaviors are simulated. This simulation was first validated through measurements of neutron response from lithium glass cylinders. With good expected light collection, an algorithm based upon the features inherent to alpha and triton particle tracks is proposed to reconstruct the neutron reaction position in the glass fiber array. Given a 1 μm fiber diameter and 0.1mm detector thickness, the neutron spatial resolution is expected to reach σ∼1 μm with a Gaussian fit in each lateral dimension. The detection efficiency was estimated to be 3.7% for a glass fiber assembly with thickness of 0.1mm. When the detector thickness increases from 0.1mm to 1mm, the position resolution is not expected to vary much, while the detection efficiency is expected to increase by about a factor of ten.
authors.affiliation: Key Discipline Laboratory of Nuclear Safety and Simulation Technology, Harbin Engineering University, Harbin 150001, China.
authors.forename: Yushou
authors.initials: Y
authors.lastname: Song
authors.affiliation: Nuclear Engineering Department, University of Tennessee, Knoxville, TN 37996, USA.
authors.forename: Joseph
authors.initials: J
authors.lastname: Conner
authors.affiliation: Nuclear Engineering Department, University of Tennessee, Knoxville, TN 37996, USA.
authors.forename: Xiaodong
authors.initials: X
authors.lastname: Zhang
authors.affiliation: Nuclear Engineering Department, University of Tennessee, Knoxville, TN 37996, USA. Electronic address: jhayward@utk.edu.
authors.forename: Jason P
authors.initials: JP
authors.lastname: Hayward
mesh_terms: D000465:Algorithms; D003198:Computer Simulation; D017076:Computer-Aided Design; D004867:Equipment Design; D019544:Equipment Failure Analysis; D005898:Glass / Q000737:chemistry / Q000528:radiation effects; D008904:Miniaturization; D015233:Models, Statistical; D009010:Monte Carlo Method; D009502:Neutrons; D011829:Radiation Dosage; D011874:Radiometry / Q000295:instrumentation*; D015203:Reproducibility of Results; D012542:Scattering, Radiation; D012588:Scintillation Counting / Q000295:instrumentation*; D012680:Sensitivity and Specificity; D012984:Software
keywords: Glass scintillator; High spatial resolution; Monte Carlo simulation; Simulation; Slow neutron detector