Study of the improvement of TLD cards for personal neutron dosimetry

Rabie, N.; Hassan, G.M.; El-Sersy, A.R.; Ezzat, M.

doi:10.1080/10420151003587674

Cited by 4 publications

(4 citation statements)

References 6 publications

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“…The TLD-600 and TLD-700 materials are both LiF:(Mg, Ti), but TLD-700 is enriched with 7 Li and contains a very small amount of 6 Li, while the TLD-600 is enriched with 6 Li to the extent of about 96%. The isotope 6 Li exhibits a large thermal neutron absorption cross-section, which gives TLD-600 (95.62% 6 Li, 4.38% 7 Li) the ability to measure thermal neutron, whereas TLD-700 (0.007% 6 Li, 99.993% 7 Li) responds identically to TLD-600 to gamma radiation and charged particles, but it is practically insensitive to thermal neutrons [ 35 , 37 , 39 , 40 , 41 , 42 , 43 ]. Thanks to this property, determining the neutron flux is possible by subtracting the TLD-700 signal from the TLD-600 signal [ 44 , 45 , 46 ].…”

Section: Methodsmentioning

confidence: 99%

Characterization of Thermoluminescent Dosimeters for Neutron Dosimetry at High Altitudes

D’Avino

Ambrosino

Bedogni

et al. 2022

Sensors

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Neutrons constitute a significant component of the secondary cosmic rays and are one of the most important contributors to natural cosmic ray radiation background dose. The study of the cosmic ray neutrons’ contribution to the dose equivalent received by humans is an interesting and challenging task for the scientific community. In addition, international regulations demand assessing the biological risk due to radiation exposure for both workers and the general population. Because the dose rate due to cosmic radiation increases significantly with altitude, the objective of this work was to characterize the thermoluminescent dosimeter (TLDs) from the perspective of exposing them at high altitudes for longtime neutron dose monitoring. The pair of TLD-700 and TLD-600 is amply used to obtain the information on gamma and neutron dose in mixed neutron-gamma fields due to the present difference in 6Li isotope concentration. A thermoluminescence dosimeter system based on pair of TLD-600/700 was characterized to enable it for neutron dosimetry in the thermal energy range. The system was calibrated in terms of neutron ambient dose equivalent in an experimental setup using a 241Am-B radionuclide neutron source coated by a moderator material, polyethylene, creating a thermalized neutron field. Afterward, the pair of TLD-600/700 was exposed at the CERN-EU High-Energy Reference Field (CERF) facility in Geneva, which delivers a neutron field with a spectrum similar to that of secondary cosmic rays. The dosimetric system provided a dose value comparable with the calculated one demonstrating a good performance for neutron dosimetry.

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Section: Methodsmentioning

confidence: 99%

Characterization of Thermoluminescent Dosimeters for Neutron Dosimetry at High Altitudes

D’Avino

Ambrosino

Bedogni

et al. 2022

Sensors

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“…The radiation field around the neutron sources is always a mixed domain, i.e. various spectra of neutrons (thermal, median, fast and high energy) and gamma rays from neutron capture reaction (n,γ) are present [3,4]. The radiation dose of gamma/neutron mixed fields for radiation protection purposes has become a necessity in a number of installations since high energy particle accelerators are heavily employed in the medical, industrial and research fields.…”

Section: Introductionmentioning

confidence: 99%

“…TLD700 is enriched with 7 Li and contains a very small amount of 6 Li, while the TLD600 is enriched with 6 Li to the extent of about 96 percent. The isotope 6 Li exhibits a large thermal neutron absorption cross-section, which gives TLD600 the ability to measure thermal neutron [4,10]. The effective Z is 8.2 for both TLD-600 and TLD-700.…”

Section: Introductionmentioning

confidence: 99%

“…If a group of dosimeters (all of the same mass and geometry, containing TLD600, and TLD700) is irradiated uniformly with thermal neutrons, there will be clear and easily interpreted differences among the responses of the dosimeter types, with the TLD600 yielding a light output from the thermal neutron dose, while TLD700 would yield virtually no response to the neutrons. TLD600 dosimeters are much more sensitive to thermal neutrons than TLD700 dosimeters enriched in 7 Li which interact very weakly with thermal neutrons [3,4].…”

Section: Introductionmentioning

confidence: 99%

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Comparison of Thermoluminescence Dosimeter’s Response to Neutron and Gamma in a Mixed Radiation Field

Hassan

Ansour

Gazy³

et al. 2019

Arab Journal of Nuclear Sciences and Applications

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Measuring radiation dose in a mixed radiation field cannot be performed by using only one dosimeter, but a pair of dosimeters, TLD600 and TLD700 can be successfully used to estimate that radiation dose. Therefore, in the present study, the response of TLD600 and TLD700 to neutron/gamma mixed radiation field was deeply discussed. Moreover, the sensitivity and stability of TLD600 and TLD700 were studied. A strong correlation between TL output signal intensity of TLD700 to gamma dose appeared, with a linear coefficient of R 2 = 0.99. Likewise, a strong correlation between TL output signal intensity of TLD600 to gamma dose and neutron irradiation was also evident, with a linear coefficient of R 2 = 0.99. Thus, TLD700 can be applied to measure gamma dose with good sensitivity, while TLD600 can be applied to measure both gamma and neutron dose. Hence, a combination of TLD700 and TLD600 can be successfully employed to assess the radiation doses characterizing a mixed radiation field of neutron and gamma rays.

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Response of TLD‐600/TLD‐700 and CR‐39 to neutrons for medical dosimetry

El-Faramawy

Chopra²,

Rawash

et al. 2021

Luminescence

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In this study, thermoluminescence detectors (TLD)‐600 and TLD‐700 were used under different conditions to study neutron dosimetry for its application in medical dosimetry as albedo dosimeters. 6LiF has a high cross‐section for neutrons and is more sensitive to neutrons than to gamma radiation. Conversely, TLD‐700 showed a better response to gamma radiation. Therefore, to obtain the response for neutrons, the responses for TLD‐600 and TLD‐700 were subtracted. A cadmium sheet was used to absorb incident thermal neutrons so that detector measured only backscattered neutrons from the albedo dosimeter. A Perspex sheet was used as a moderator to thermalize the fast neutron source Am‐Be used in the experiment. CR‐39 was used to detect fast neutrons and act as an albedo dosimeter when covered with a 10B disc. Both TLD and CR‐39 dosimeters were successful in detecting scattered neutrons in radiotherapy rooms.

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Study of the improvement of TLD cards for personal neutron dosimetry

Cited by 4 publications

References 6 publications

Characterization of Thermoluminescent Dosimeters for Neutron Dosimetry at High Altitudes

Characterization of Thermoluminescent Dosimeters for Neutron Dosimetry at High Altitudes

Comparison of Thermoluminescence Dosimeter’s Response to Neutron and Gamma in a Mixed Radiation Field

Response of TLD‐600/TLD‐700 and CR‐39 to neutrons for medical dosimetry

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