2019
DOI: 10.1016/j.apradiso.2019.05.040
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Design by Monte Carlo method of a thermal neutron device using a 241Am/9Be source and high-density polyethylene moderator

Abstract: A device has been designed to increase thermal neutron flux from a 241 Am/ 9 Be source, through the neutron moderation.• The system can be used to identify trace materials by Neutron Activation Analysis.• Three different alternative moderator materials, water, graphite and high-density polyethylene (HDPE), were simulated.• The system performance was evaluated with the MCNP6 code.

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Cited by 4 publications
(1 citation statement)
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“…While concrete and lead are typical shielding materials, polyethylene and water are known moderators of neutrons, which can be used for machine calibration for radiation dosimetry and radiation protection. The use of water phantoms is a golden standard for calibrating LINAC machines for they are well-known as tissue-equivalent materials (Vega-Carillo et al, 2010;Cevallos-Robalino et al, 2019;Qi et al, 2021).…”
Section: Methodsmentioning
confidence: 99%
“…While concrete and lead are typical shielding materials, polyethylene and water are known moderators of neutrons, which can be used for machine calibration for radiation dosimetry and radiation protection. The use of water phantoms is a golden standard for calibrating LINAC machines for they are well-known as tissue-equivalent materials (Vega-Carillo et al, 2010;Cevallos-Robalino et al, 2019;Qi et al, 2021).…”
Section: Methodsmentioning
confidence: 99%