Dose Calibration and Track Diameter Distribution for 241Am-Be Neutron Source, Using CR-39 Nuclear Track Methodology

  • J. S. Bogard Oak Ridge National Laboratory (ORNL), Oak Ridge, TN 37831-6480, USA
  • J. I. Golzarri Institute of Physics, National Autonomous University of Mexico (UNAM), 04520 Mexico City, Mexico
  • G. Espinosa Institute of Physics, National Autonomous University of Mexico (UNAM), 04520 Mexico City, Mexico
Keywords: Americium beryllium neutron source, track density imaging, CR-39 Nuclear Track, chemical etching process


In neutron detection, the more common method is using electronic instrumentation associate with Bonner spheres, however, currently the Nuclear Tracks Methodology (NTM) is coming popular because of the simplicity, flexibility in size of the detector, no requirement for sophisticated instrumentation and installation, and low cost. In this work, a preliminary result of the dose calibration and track diameter distribution of Americium-Beryllium (241Am-Be) source using Nuclear Track Methodology is presented. As material detector, CR-39 polycarbonate, cut in 1.8 × 0.9 cm2 chips was chosen, and two step chemical etchings after neutron exposure was used to develop the tracks. The irradiations were made in environmental normal conditions, in the ORNL neutron calibration facilities. The CR-39 chips were placed in a phantom, with 3mm plastic (Lexan) sheet in between the source and detectorsto increase the proton generation. The total track density and track diameter distribution was performing in a Counting and Analysis Digital Image System (CADIS), developed at the Institute of Physics of the University of Mexico UNAM. The results are compared with a standard survey instrument and energy reference spectra of the International Atomic Energy Agency (IAEA).


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How to Cite
J. S. Bogard; J. I. Golzarri; G. Espinosa. Dose Calibration and Track Diameter Distribution for 241Am-Be Neutron Source, Using CR-39 Nuclear Track Methodology. J. Nucl. Phy. Mat. Sci. Rad. A. 2018, 6, 77-80.