Fast-neutron detector developments for the TREAT hodoscope

  title={Fast-neutron detector developments for the TREAT hodoscope},
  author={Jeremy A. Roberts and Mark J. Harrison and Wenkai Fu and Priyarshini Ghosh and Douglas S. Mcgregor},
  journal={Radiation Physics and Chemistry},
Abstract This work describes the theoretical and experimental performances of four alternatives to the original Hornyak Button-type device that was used in the construction of the Transient Reactor Test (TREAT) Facility hodoscope. The alternatives considered differ in geometry, construction and detection materials to improve performance while decreasing some of the negative aspects of the original device. A Geant4 model of the original Hornyak Button was developed as a benchmark to validate the… 
Modeling and simulation of neutron detectors for the transient reactor test facility
  • W. Fu
  • Materials Science
  • 2019
The Transient REActor Test (TREAT) facility was restarted and will be used to test accident-tolerant fuels to improve nuclear reactor safety. In this work, alternative neutron detectors for use in
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Numerical evaluation of fast-sensitive microstructured semiconductor neutron detectors for TREAT hodoscope
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Characterization and pulse-shape discrimination of a multi-stacked structure of ZnS: Ag/PMMA for fast-neutron detection in high-flux environments
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A description is given of a fast-neutron hodoscope to detect fuel motion within test samples inserted in the center of the Transient Reactor Test Facility (TREAT) reactor core. The fuel motion is
High-efficiency microstructured semiconductor neutron detectors that are arrayed, dual-integrated, and stacked.
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A fast neutron detector with an efficiency of a few percent and the capability of detecting neutrons in the presence of intense gamma‐ray backgrounds has been developed. The detector consists of a
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In this paper results from hodoscope data analyses are presented for transient overpower (TOP) tests M5, M6, and M7 at the Transient Reactor Test Facility, with emphasis on transient feedback
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Abstract SRIM is a software package concerning the S topping and R ange of I ons in M atter. Since its introduction in 1985, major upgrades are made about every six years. Currently, more than 700
Geant4 - A simulation toolkit
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High confidence in the MCNP6 code is based on its performance with the verification and validation test suites, comparisons to its predecessor codes, the regression test suite, its code development process, and the underlying high-quality nuclear and atomic databases.
Evaluation of msnds for fast-neutron detection and the treat hodoscope
  • Trans. Am. Nucl. Soc.
  • 2016