Neutron-gamma mixed field dosimetry using a 6LiF:Mg,Cu,P thermoluminescent dosimeter
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Published:2021
Issue:4
Volume:36
Page:346-351
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ISSN:1451-3994
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Container-title:Nuclear Technology and Radiation Protection
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language:en
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Short-container-title:NUCL TECH RAD PROT
Author:
Sadeghi Ehsan1, Zahedifar Mostafa1, Rezaii Parasto2
Affiliation:
1. Physics Department, University of Kashan, Kashan, Iran + Institute of Nanoscience and Nanotechnology, University of Kashan, Kashan, Iran 2. Physics Department, University of Kashan, Kashan, Iran
Abstract
Satisfactory discrimination between the neutron and gamma components in a
mixed neutron-gamma field is one of the most important objectives of
neutron dosimetry. One of the common techniques for estimating gamma and
neutron dose components in mixed neutron-gamma fields is the two peak
method. This method has been applied using dosimeters such as LiF:Mg,Ti, but
in the present work, a 6LiF:Mg,Cu,P dosimeter has been used, whose
thermoluminescence sensitivity is much higher than the LiF:Mg,Ti dosimeter,
and therefore, if appropriate results are achieved, it can drastically
reduce the dose estimation threshold. Applicability of 6LiF:Mg,Cu,P for
estimation of the gamma dose using the two peak method in a mixed thermal
neutron-gamma radiation field was studied. The ratio of the area underneath
the high temperature thermoluminescence glow peak to dosimetry peak of this
phosphor in an Am-Be neutron field is 0.127, while this ratio in a pure
gamma ray field of 137Cs is 0.039. The calibration curves were obtained by
separately irradiating 6LiF:Mg,Cu,P chips with known gamma and neutron
doses. Results show that 6LiF:Mg,Cu,P can be used to estimate the
contributions of neutron and gamma doses in a mixed neutron-gamma field by
using the two peak method.
Publisher
National Library of Serbia
Subject
Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering
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