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

Main Authors: J. S. Bogard, J. I. Golzarri, G. Espinosa
Format: Article info Book application/pdf
Bahasa: eng
Terbitan: Chitkara University Publications , 2018
Subjects:
Online Access: https://jnp.chitkara.edu.in/index.php/jnp/article/view/43
https://jnp.chitkara.edu.in/index.php/jnp/article/view/43/24
ctrlnum article-43
fullrecord <?xml version="1.0"?> <dc schemaLocation="http://www.openarchives.org/OAI/2.0/oai_dc/ http://www.openarchives.org/OAI/2.0/oai_dc.xsd"><title lang="en-US">Dose Calibration and Track Diameter Distribution for 241Am-Be Neutron Source, Using CR-39 Nuclear Track Methodology</title><creator>J. S. Bogard</creator><creator>J. I. Golzarri</creator><creator>G. Espinosa</creator><subject lang="en-US">Americium beryllium neutron source</subject><subject lang="en-US">track density imaging</subject><subject lang="en-US">CR-39 Nuclear Track</subject><subject lang="en-US">chemical etching process</subject><description lang="en-US">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 &#xD7; 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).</description><publisher lang="en-US">Chitkara University Publications</publisher><date>2018-08-06</date><type>Journal:Article</type><type>Other:info:eu-repo/semantics/publishedVersion</type><type>Book:Book</type><type>File:application/pdf</type><identifier>https://jnp.chitkara.edu.in/index.php/jnp/article/view/43</identifier><identifier>10.15415/jnp.2018.61013</identifier><source lang="en-US">Journal of Nuclear Physics, Material Sciences, Radiation and Applications; Vol 6 No 1 (2018); 77-80</source><source>2321-9289</source><source>2321-8649</source><language>eng</language><relation>https://jnp.chitkara.edu.in/index.php/jnp/article/view/43/24</relation><rights lang="en-US">Copyright (c) 2018 Journal of Nuclear Physics, Material Sciences, Radiation and Applications</rights><rights lang="en-US">https://creativecommons.org/licenses/by/4.0/</rights><recordID>article-43</recordID></dc>
language eng
format Journal:Article
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File:application/pdf
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author J. S. Bogard
J. I. Golzarri
G. Espinosa
title Dose Calibration and Track Diameter Distribution for 241Am-Be Neutron Source, Using CR-39 Nuclear Track Methodology
publisher Chitkara University Publications
publishDate 2018
topic Americium beryllium neutron source
track density imaging
CR-39 Nuclear Track
chemical etching process
url https://jnp.chitkara.edu.in/index.php/jnp/article/view/43
https://jnp.chitkara.edu.in/index.php/jnp/article/view/43/24
contents 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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