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Sadeghi E, Zahedifar M, Rezaii P. Neutron-gamma mixed field dosimetry using a 6LiF:Mg,Cu,P thermoluminescent dosimeter. NUCLEAR TECHNOLOGY AND RADIATION PROTECTION 2021. [DOI: 10.2298/ntrp2104346s] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/27/2022] Open
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.
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Affiliation(s)
- Ehsan Sadeghi
- Physics Department, University of Kashan, Kashan, Iran + Institute of Nanoscience and Nanotechnology, University of Kashan, Kashan, Iran
| | - Mostafa Zahedifar
- Physics Department, University of Kashan, Kashan, Iran + Institute of Nanoscience and Nanotechnology, University of Kashan, Kashan, Iran
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Lin JB, Tseng HC, Liu WS, Lin DB, Hsieh TS, Chen CY. Evaluating secondary neutron doses of a refined shielded design for a medical cyclotron using the TLD approach. Radiat Phys Chem Oxf Engl 1993 2013. [DOI: 10.1016/j.radphyschem.2013.06.019] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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