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Neutron spectrometry using CR-39 track etch detectors.

Gary W Phillips1, Jerrette E Spann, James S Bogard

  • 1Georgetown University, Radiation Medicine Department, 3970 Reservoir Road NW, Research Building Room E202A, Washington, DC 20057-1482, USA. phillipg@georgetown.edu

Radiation Protection Dosimetry
|June 1, 2006
PubMed
Summary

Track-size distributions in CR-39 foils reveal neutron energy and source characteristics. Automated analysis distinguishes neutron sources, including plutonium-238 fission, from background radiation.

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Area of Science:

  • Nuclear Physics
  • Radiation Detection and Measurement

Background:

  • CR-39 (allyl diglycol carbonate) plastic is a widely used solid-state nuclear track detector.
  • Neutron interactions with CR-39 produce charged particles that form etchable tracks.
  • Track characteristics depend on neutron energy, particle type, and incidence angle.

Purpose of the Study:

  • To characterize track-size distributions in CR-39 foils exposed to various neutron sources.
  • To evaluate the potential of track-size analysis for neutron spectrometry and source identification.

Main Methods:

  • Exposure of CR-39 foils to monoenergetic neutrons (0.144-19 MeV) and broad-spectrum sources (including 238Pu fission).
  • Chemical etching of CR-39 foils to reveal charged particle tracks.
  • Automated analysis system for scanning foils, identifying tracks, and measuring track-size parameters.

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Main Results:

  • Track-size distributions varied significantly with neutron energy for monoenergetic sources.
  • Broad-spectrum sources yielded distinct track-size distributions based on their spectral hardness.
  • The track-size distribution from 238Pu fission neutrons was uniquely identifiable and distinguishable from background.

Conclusions:

  • Automated track-size analysis of CR-39 foils is effective for characterizing neutron fields.
  • This method allows for the differentiation of various neutron sources, including distinguishing 238Pu fission neutrons.
  • CR-39 dosimetry offers a viable technique for neutron spectrometry and source identification in radiation monitoring.