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Journal articles on the topic 'Thermoluminescent Dosimeters'

Author: Grafiati

Published: 4 June 2021

Last updated: 11 February 2022

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1

Bhatt, B. C., and M. S. Kulkarni. "Thermoluminescent Phosphors for Radiation Dosimetry." Defect and Diffusion Forum 347 (December 2013): 179–227. http://dx.doi.org/10.4028/www.scientific.net/ddf.347.179.

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The use of thermoluminescence (TL) as a method for radiation dosimetry of ionizing radiation has been established for many decades and has found many useful applications in various fields, such as personnel and environmental monitoring, retrospective dosimetry, medical dosimetry, space dosimetry, high-dose dosimetry. Method of preparation, studies and applications of thermoluminescence (TL) dosimetric materials are reviewed. Several high sensitivity thermoluminescent dosimeters (TLDs) are now commercially available in different physical forms. These commercial TL dosimeters comply with a set of stringent requirements stipulated by the International Electrotechnical Commission (IEC). Specific features of TL phosphors for thermal neutron, fast neutron and high-energy charged particle (HCP) dosimetry are also considered. Some of the recent developments in the field of optically stimulated luminescence (OSL) and radiophotoluminescence (RPL) are also summarized. Comparative advantages of TL, OSL and RPL dosimeters are given. Results of recent studies of TL in nanosized materials are briefly presented. Future challenges in this field will also be discussed. Contents of Paper

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2

Gasiorowski, Andrzej, Piotr Szajerski, and Jose Francisco Benavente Cuevas. "Use of Terbium Doped Phosphate Glasses for High Dose Radiation Dosimetry—Thermoluminescence Characteristics, Dose Response and Optimization of Readout Method." Applied Sciences 11, no. 16 (August 5, 2021): 7221. http://dx.doi.org/10.3390/app11167221.

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The phosphate glass samples doped with Tb2O3 oxide (general formula: P2O5-Al2O3-Na2O-Tb2O3) were synthesized and studied for usage in high-dose radiation dosimetry (for example, in high-activity nuclear waste disposals). The influence of terbium concentration on thermoluminescent (TL) signals was analyzed. TL properties of glasses were investigated using various experimental techniques such as direct measurements of TL response vs. radiation dose, Tmax–Tstop and VHR (various heating rate) methods, and glow curve deconvolution analysis. The thermoluminescence dosimetry (TLD) technique was used as the main investigation tool to study detectors’ dose responses. It has been proved that increasing the concentration of terbium oxide in glass matrices significantly increases the thermoluminescence yield of examined material. For the highest dose range (up to 35 kGy), the dependence of the integrated thermoluminescent signals vs. dose can be considered as a saturation-type curve. Additional preheating of samples improves linearity of signal vs. dose dependencies and leads to a decrease of the signal loss over time. All obtained data suggest that investigated material can be used in high-dose radiation dosimetry. Additional advantages of the investigated dosimetric system are its potential ability to re-use the same dosimeters multiple times and the fact that reading dosimeters only requires usage of a basic TL reader without any modifications.

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3

West, William Geoffrey, and Kimberlee Jane Kearfott. "Optically Stimulated Luminescence Dosimetry: An Introduction." Solid State Phenomena 238 (August 2015): 161–73. http://dx.doi.org/10.4028/www.scientific.net/ssp.238.161.

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A subset of solid state materials have long been used as integrating dosimeters because they store energy deposited as a result of their interactions with ionizing radiation and then, when stimulated appropriately, release a proportionate amount of visible or near-visible light. During the 1960s, thermoluminescent dosimeters (TLDs), for which heat is used to extract the stored dosimetric signal, began to replace the photographic film as occupational dosimeters of record and for medical dosimetry. At the end of the twentieth century, a viable optically stimulated luminescent (OSL) material was developed which is now gaining in popularity as both an occupational and medical dosimeter. This paper reviews the related stored luminescence processes, presenting a simple conceptual model for optical absorption transitions in OSL materials along with a basic mathematical model for delayed luminescence. The approaches for extracting signal from the OSLs are enumerated.

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Barros, Silvia, and Geehyun Kim. "Response assessment of a new albedo neutron dosimeter." International Journal of Modern Physics: Conference Series 48 (January 2018): 1860111. http://dx.doi.org/10.1142/s2010194518601114.

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The use of thermoluminescent dosimeters (TLDs) by personnel who work in radiation-rich environments is required by law. However, many professionals prefer to use Electronic Personal Dosimeters (EPDs), which provide dose estimation in real time. This preference may lead to a generalized use of the EPD instead of using the required TLD, as the use of both types at once can be uncomfortable and impractical. In an effort to avoid this scenario, a gamma/neutron dosimeter composed of a TLD and an EPD is being developed. In this paper, the results obtained from the studies performed in order to develop the neutron albedo dosimeter to be incorporated in the TLD[Formula: see text]EPD dosimeter are presented. Monte Carlo simulations using the state-of-the-art Monte Carlo N-Particle Transport (MCNPX) code were used to calculate the response of the albedo dosimeter. The thermal neutron detectors under consideration for use in the proposed dosimeter are the EJ-426 and the EJ-420. Both detectors employ a lithium compoundenriched to 95% [Formula: see text]Li dispersed in a ZnS:(Ag) matrix. The tomographic phantom Korean Typical Man-2 was used in the simulations to calculate the fraction of radiation backscattered by a human body in different radiation field conditions. From these results, it was concluded that both dosimeters are fit to be used as albedo dosimeters.

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Pyshkina, Mariya, Mihail Zhukovskiy, Aleksey Vasil'ev, and Marina Romanova. "Oral Thermoluminescent Neutron Dosimeter for Emergency Exposure Conditions." ANRI, no. 2 (June 29, 2021): 65–74. http://dx.doi.org/10.37414/2075-1338-2021-105-2-65-74.

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An oral dosimeter of mixed gamma-neutron radiation for emergency exposure conditions has been developed. The energy dependence of the neutron radiation dosimeter sensitivity is close to the energy dependence of the specific effective dose per unit flux density. For neutron fields containing a significant contribution of fast neutrons, the uncertainty of the dosimeter readings is no more than 25% for the anteroposterior radiation geometry and no more than 35% for the rotation geometry. In neutron fields with a predominance of particles with thermal and intermediate energies, the dosimeter overestimates the effective radiation dose by 2.5 times for the anteroposterior geometry and 3.3 times for the rotation geometry. A staging experiment was carried out, which included placing individual dosimeters inside a canister simulating the torso of a standard adult in a neutron radiation field. The conditionally true values of the effective dose were obtained using the energy and angular distribution of the neutron radiation flux density. Differences in the dosimeter readings and the conditionally true value of the effective dose do not exceed 2.

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6

Adamiv, V., Ya Burak, I. Teslyuk, O. Antonyak, I. Moroz, and S. Malynych. "LiB3O5 pyroceramic for thermoluminescent dosimeters." Ukrainian Journal of Physical Optics 20, no. 4 (2019): 159–67. http://dx.doi.org/10.3116/16091833/20/4/159/2019.

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7

Shleenkova, Ekaterina N., Vladislav Yu Golikov, Georgy N. Kaidanovsky, Stepan Yu Bazhin, and Vladimir A. Ilyin. "Results of eye lens doses control of medical personnel in St. Petersburg." Radiatsionnaya Gygiena = Radiation Hygiene 12, no. 4 (January 7, 2020): 29–36. http://dx.doi.org/10.21514/1998-426x-2019-12-4-29-36.

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Results of individual monitoring for personnel of X-ray surgical teams in several clinics of St. Petersburg are presented and analyzed. Measurements of the operational quantities – individual dose equivalents Hp (3) and Hp (10) were performed by thermoluminescent dosimetry method. Dosimeters designed to measure Hp (3) were located in the operators forehead area, and to determine Hp (10) both above the operator ‘s individual protective apron in the collar or chest area and under the protective apron in the chest area. The results of 34 measurements of the annual values of Hp (3) and Hp (10) measured above the apron and 24 values of Hp (10) measured below the apron were processed and analyzed. The results after the statistical treatment show that the probability of exceeding the annual values of Hp (3) in the personnel of X-ray surgical teams of the new dose limit 20 mSv is small, less than 1%. Exceeding the current dose limit of the equivalent exposure dose of the lens of the eye (150 mSv) is hardly possible at all under normal conditions. The best solution for evaluating the radiation dose of the lens of the eye is to measure the individual equivalent of the dose Hp (3), using a suitably calibrated TL-dosimeter (thermoluminescent dosimeter) located near the worker’s eyes. However, this additional dosimeter is only necessary when the values of eye lens equivalent dose can approach the new value of dose limit of 20 mSv. According to the results of the study, it is possible to introduce such an additional dosimeter if the annual value of Hp (10) recorded by the dosimeter located above the protective apron is more than 10 mSv.

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8

Martin, S., A. Lisbona, J. Richard, S. Morteau, B. Denizot, and M. Bardiès. "Production of new thermoluminescent mini-dosimeters." Physics in Medicine and Biology 45, no. 2 (January 25, 2000): 479–94. http://dx.doi.org/10.1088/0031-9155/45/2/315.

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9

Manzoli, José Eduardo, Vicente de Paulo de Campos, and Mirian Saori Doi. "Evaluation of reproductibility and detection limit of CaSO4: dy radiation detectors." Brazilian Archives of Biology and Technology 49, spe (January 2006): 53–58. http://dx.doi.org/10.1590/s1516-89132006000200009.

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Measurement response of thermoluminescent dosimeter, TLD, used by workers or placed at positions where gamma radiation field could be in action affecting biological tissues, should be completely characterized, in order to achieve the radiation quantity with precision and confidence. Among the evaluations concerned to its characterization, the detector reproductibility is of fundamental importance, because detectors present inside the TLD will be used many times in routine. Reproductibility is studied by repeated exposure to the same radiation field. The minimum detection limit is another important characteristics of a TLD. In this work evaluations of reproductibility and minimum detection are presented, for dosimeters produced at IPEN.

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10

Sohrabi, M., M. Jafarizadeh, and M. Zahedifar. "Kinetic parameters of LiF:Mg,Ti thermoluminescent dosimeters." Radiation Physics and Chemistry 51, no. 4-6 (June 1998): 401–2. http://dx.doi.org/10.1016/s0969-806x(97)00154-0.

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11

Mansy, M., A. Hussein, A. A. Higazy, A. M. Sayed, and M. Sharaf. "The MgO-P2O5glasses as thermoluminescent gamma dosimeters." Radiation Effects and Defects in Solids 145, no. 1-2 (July 1998): 115–21. http://dx.doi.org/10.1080/10420159808220027.

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12

Costa, Alessandro M., Gustavo L. Barbi, Edenyse C. Bertucci, Heberton Ferreira, Simone Z. Sansavino, Beatriz Colenci, and Linda V. E. Caldas. "In vivo dosimetry with thermoluminescent dosimeters in external photon beam radiotherapy." Applied Radiation and Isotopes 68, no. 4-5 (April 2010): 760–62. http://dx.doi.org/10.1016/j.apradiso.2009.09.039.

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13

Ahmad, Habib, Shahid Ali, Sohail Roomi, Yaseen Iqbal, Muhammad Ajmal, Khizar Hayat, and Syed Zulfiqar. "Conversion of LiF-based thermoluminescent dosimeters into photoluminescent dosimeters via Dy doping." Materials Research Express 4, no. 10 (October 17, 2017): 105015. http://dx.doi.org/10.1088/2053-1591/aa8ebf.

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14

Bastos, F. C., W. J. Castro, P. L. Squair, M. S. Nogueira, and T. A. Da Silva. "Feasibility of calibrating thermoluminescent dosimeters in a mammography unit for patient dosimetry." Radiation Measurements 46, no. 12 (December 2011): 2094–96. http://dx.doi.org/10.1016/j.radmeas.2011.06.032.

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15

Rocha, Felı́cia D. G., Mércia L. Oliveira, Sonia G. P. Cecatti, and Linda V. E. Caldas. "Properties of sintered amethyst pellets as thermoluminescent dosimeters." Applied Radiation and Isotopes 58, no. 1 (January 2003): 85–88. http://dx.doi.org/10.1016/s0969-8043(02)00266-x.

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16

Plato, Phillip, and Joseph Miklos. "Production of Element Correction Factors for Thermoluminescent Dosimeters." Health Physics 49, no. 5 (November 1985): 873–81. http://dx.doi.org/10.1097/00004032-198511000-00019.

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17

Azorín, C., J. Azorín, F. Aguirre, and T. Rivera. "Dose measurements in intraoral radiography using thermoluminescent dosimeters." Journal of Physics: Conference Series 582 (January 14, 2015): 012006. http://dx.doi.org/10.1088/1742-6596/582/1/012006.

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18

Azorin, Juan, and Alicia Gutierrez. "Environmental monitoring using thermoluminescent dosimeters prepared at ININ." International Journal of Radiation Applications and Instrumentation. Part C. Radiation Physics and Chemistry 38, no. 2 (January 1991): 267. http://dx.doi.org/10.1016/1359-0197(91)90284-9.

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19

Del Sol Fernández, S., R. García-Salcedo, D. Sánchez-Guzmán, G. Ramírez-Rodríguez, E. Gaona, M. A. de León-Alfaro, and T. Rivera-Montalvo. "Thermoluminescent dosimeters for low dose X-ray measurements." Applied Radiation and Isotopes 107 (January 2016): 340–45. http://dx.doi.org/10.1016/j.apradiso.2015.11.021.

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20

Damulira, Edrine, Muhammad Nur Salihin Yusoff, Ahmad Fairuz Omar, and Nur Hartini Mohd Taib. "A Review: Photonic Devices Used for Dosimetry in Medical Radiation." Sensors 19, no. 10 (May 14, 2019): 2226. http://dx.doi.org/10.3390/s19102226.

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Numerous instruments such as ionization chambers, hand-held and pocket dosimeters of various types, film badges, thermoluminescent dosimeters (TLDs) and optically stimulated luminescence dosimeters (OSLDs) are used to measure and monitor radiation in medical applications. Of recent, photonic devices have also been adopted. This article evaluates recent research and advancements in the applications of photonic devices in medical radiation detection primarily focusing on four types; photodiodes – including light-emitting diodes (LEDs), phototransistors—including metal oxide semiconductor field effect transistors (MOSFETs), photovoltaic sensors/solar cells, and charge coupled devices/charge metal oxide semiconductors (CCD/CMOS) cameras. A comprehensive analysis of the operating principles and recent technologies of these devices is performed. Further, critical evaluation and comparison of their benefits and limitations as dosimeters is done based on the available studies. Common factors barring photonic devices from being used as radiation detectors are also discussed; with suggestions on possible solutions to overcome these barriers. Finally, the potentials of these devices and the challenges of realizing their applications as quintessential dosimeters are highlighted for future research and improvements.

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21

Oh, H., S. Sung, S. Lim, Y. Jung, Y. Cho, and K. Lee. "Restrainer exposure to scatter radiation in practical small animal radiography measured using thermoluminescent dosimeters." Veterinární Medicína 63, No. 2 (February 22, 2018): 81–86. http://dx.doi.org/10.17221/115/2017-vetmed.

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This study was aimed at estimating restrainer exposure to scatter radiation in veterinary radiography using thermoluminescent dosimeters (TLDs) in different positions, and at different anatomic regions. A prospective study was conducted to measure exposure dose of two restrainers: A (cathode side) and B (anode side), and an observer C (at a 1-meter distance from the X-ray table) over two months. Protective devices included panorama mask, thyroid shield and arm shield. TLDs were placed on the inside and outside of the protective gear at five different anatomic sites (eye, thyroid, breast, gonad and arm). The study data consisted of 778 exposures, 82 patients (78 dogs, four cats), a mean kVp of 58.7 and a mean mAs of 11.4. The doses (outside the shield/inside the shield, in mSv) measured by restrainers A, B and C were eye (3.04/0.42), (2.29/0.17), (0.55/0.01), thyroid (2.93/0.01), (1.97/0.01), (0.19/0.01), breast (1.01/0.04), (0.73/0.01), (0.32/0.01), gonad (0.07/0.01), (0.01/0.01), (0.16/0.01) and arm (2.81/1.43), (1.17/0.01), (0.08/0.01), respectively. This study describes the extent of occupational radiation exposure in small animal radiography. The exposure dose for eyes outside lead protection showed the highest value in all participants. With lead protection, the reduction in the exposure dose of eyes was significant (A: 86%, B: 93%, C: 98%), and the highest reduction was 99% in the thyroid region. These results suggest the necessity of radiation shields in manual restraint, particularly for eye protection.

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22

Miloichikova, Irina, Sergei Stuchebrov, Angelina Krasnykh, and Alexander Wagner. "Radiation Dose Measurement Technique of the X-Ray Source in the Process of Stabilization." Advanced Materials Research 1085 (February 2015): 478–81. http://dx.doi.org/10.4028/www.scientific.net/amr.1085.478.

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In the article the radiation burden measurement technique of the X-ray source in the process of stabilization is described. The possibility of using this technique for the dose rate determination from the pulsed X-ray source is presented. The measurement technique approbation results at the pulsed X-ray source RAP-160-5 using thermoluminescent dosimeters DTL-02 are shown.

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23

Radaideh, Khaldoon. "Evaluation of thermoplastic Klarity mask use during intensity-modulated radiation therapy for head and neck carcinoma." Journal of Radiotherapy in Practice 17, no. 2 (January 8, 2018): 171–78. http://dx.doi.org/10.1017/s1460396917000632.

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AbstractAimTo evaluate the Klarity® Mask with respect to skin doses and toxicity secondary to head and neck cancer radiation treatment.Materials and methodsThis prospective study included five nasopharyngeal cancer patients who underwent intensity-modulated radiation therapy and monitored for skin toxicity. An anatomical Perspex head and neck phantom was designed and used. All patients’ treatment plans were separately transferred to the phantom. Dosimetric measurements were performed using chip-shaped thermoluminescent dosimeters (LiF:Mg,Ti TLDs) which were distributed at certain target points on the phantom. Phantom was irradiated twicely with and without a Klarity® Mask. Three fractions for each patient plan were obtained and compared with treatment planning system (TPS) doses as guided by computed tomography.ResultsThe Klarity mask used for patient immobilisation increased the surface dose by 10·83% more than that without the mask. The average variations between skin dose measurements with and without the Klarity mask for all patients’ plans ranged from 10·26 to 11·83%. TPS overestimated the surface dose by 19·13% when compared with thermoluminescent dosimeters that measured the direct skin dose.ConclusionsKlarity immobilisation mask increases skin doses, as a consequence, surface dose measurements should be monitored and must be taken into account.

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24

Harvey, John A., and Kimberlee J. Kearfott. "Reproducibility of glow peak fading characteristics of thermoluminescent dosimeters." Radiation Measurements 46, no. 3 (March 2011): 319–22. http://dx.doi.org/10.1016/j.radmeas.2011.01.005.

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25

Karpov, D. N., N. A. Karpov, and V. N. Gus’kov. "Glow curve analysis applied to solid-state thermoluminescent dosimeters." Inorganic Materials 42, no. 10 (October 2006): 1152–58. http://dx.doi.org/10.1134/s0020168506100189.

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26

Alqahtani, Amal, D. A. Bradley, Abdulaziz Alanazi, and Andrew Nisbet. "Characterisation of borosilicate glass media as potential thermoluminescent dosimeters." Radiation Physics and Chemistry 168 (March 2020): 108630. http://dx.doi.org/10.1016/j.radphyschem.2019.108630.

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27

Mumford, J. W., L. M. Apátiga, J. I. Golzarri, and V. M. Castaño. "Stability of polycrystalline diamond films as UV thermoluminescent dosimeters." Materials Letters 37, no. 6 (December 1998): 330–33. http://dx.doi.org/10.1016/s0167-577x(98)00115-3.

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28

Fominykh, V. I., A. V. Oborin, A. P. Sebekin, and I. A. Uryaev. "Methods and means of checking thermoluminescent and radiophotoluminescent dosimeters." Measurement Techniques 30, no. 1 (January 1987): 108–11. http://dx.doi.org/10.1007/bf00865744.

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29

Cortés, J. Rodríguez, R. Alvarez Romero, J. Azorín Nieto, and T. Rivera Montalvo. "Electron absorbed dose measurements in LINACs by thermoluminescent dosimeters." Applied Radiation and Isotopes 83 (January 2014): 210–13. http://dx.doi.org/10.1016/j.apradiso.2013.06.013.

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30

Franssen, R., M. G. W. Visser, C. J. A. Urbach, S. G. E. A. Halders, M. J. Frantzen, B. Brans, G. J. J. Teule, F. M. Mottaghy, and G. J. Kemerink. "Hard beta and gamma emissions of 124I." Nuklearmedizin 50, no. 06 (2011): 240–46. http://dx.doi.org/10.3413/nukmed-0414-11-06.

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SummaryAim: The hard beta and gamma radiation of 124I can cause high doses to PET/CT workers. In this study we tried to quantify this occupational exposure and to optimize radioprotection. Methods: Thin MCP-Ns thermoluminescent dosimeters suitable for measuring beta and gamma radiation were used for extremity dosimetry, active personal dosimeters for whole-body dosimetry. Extremity doses were determined during dispensing of 124I and oral administration of the activity to the patient, the body dose during all phases of the PET/CT procedure. In addition, dose rates of vials and syringes as used in clinical practice were measured. The procedure for dispensing 124I was optimized using newly developed shielding. Results: Skin dose rates up to 100 mSv/ min were measured when in contact with the manufacturer's vial containing 370 MBq of 124I. For an unshielded 5 ml syringe the positron skin dose was about seven times the gamma dose. Before optimization of the preparation of 124I, using an already reasonably safe technique, the highest mean skin dose caused by handling 370 MBq was 1.9 mSv (max. 4.4 mSv). After optimization the skin dose was below 0.2 mSv. Conclusion: The highly energetic positrons emitted by 124I can cause high skin doses if radioprotection is poor. Under optimized conditions occupational doses are acceptable. Education of workers is of paramount importance.

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An, J., S. Lim, S. Lee, H. Kim, K. Min, Y. Cho, and K. Lee. "Evaluation of radiation exposure from fluoroscopic examination in small animal veterinary staff using thermoluminescent dosimeters." Veterinární Medicína 64, No. 6 (June 20, 2019): 266–70. http://dx.doi.org/10.17221/141/2018-vetmed.

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The purpose of this study was to evaluate the occupational radiation exposure levels of veterinary staff during fluoroscopic examination using thermoluminescent dosimeters (TLDs). A prospective study was conducted to measure radiation doses in three positioned persons (two restrainers and one observer) using TLDs. The TLDs were placed on the inside and outside of the lead-equivalent protective devices of the panorama mask, thyroid shield, apron and arm shield. The TLDs were placed at five anatomic sites (eye, thyroid, breast, gonad and hand). Radiation exposure was measured in 65 fluoroscopic examinations at 80 kVp and 100 mAs. The doses (mSv) (outside/inside the shield) measured in restrainers A and B and observer C were 3.09/0.59, 3.80/0.65 and 0.63/0.44 in the eye; 2.20/0.73, 1.88/1.10 and 0.79/0.45 in the thyroid; 3.42/0.44, 3.94/2.35 and 0.61/0.34 in the breast; 1.84/0.45, 1.69/0.23 and 0.46/0.36 in the gonad; and 5.56/3.16, 8.29/2.99 and 0.79/0.34 in the hand, respectively. Out of all the lead protection devices, the radiation dose of the hand was the highest in all three participants, with the thyroid radiation dose value being the same as the hand in the observer C. Radiation doses received by the eyes of all three participants were also not negligible. Veterinary workers exposed to radiation through not only radiography but also fluoroscopy should wear protective gear, especially for the eyes.

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32

Radaideh, Khaldoon M., Laila M. Matalqah, A. A. Tajuddin, W. I. Fabian Lee, S. Bauk, and E. M. Eid Abdel Munem. "Development and evaluation of a Perspex anthropomorphic head and neck phantom for three dimensional conformal radiation therapy (3D-CRT)." Journal of Radiotherapy in Practice 12, no. 3 (April 22, 2013): 272–80. http://dx.doi.org/10.1017/s1460396912000453.

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AbstractPurposesTo design, construct and evaluate an anthropomorphic head and neck phantom for the dosimetric evaluation of 3D-conformal radiotherapy (3D-CRT) dose planning and delivery, for protocols developed by the Radiation Therapy Oncology Group (RTOG).Materials and methodsAn anthropomorphic head and neck phantom was designed and fabricated using Perspex material with delineated planning target volumes (PTVs) and organs at risk (OARs) regions. The phantom was imaged, planned and irradiated conformally by a 3D-CRT plan. Dosimetry within the phantom was assessed using thermoluminescent dosimeters (TLDs). The reproducibility of phantoms and TLD readings were checked by three repeated identical irradiations. Subsequent three clinical 3D-CRT plans for nasopharyngeal patients have been verified using the phantom. Measured doses from each dosimeter were compared with those acquired from the treatment planning system (TPS).ResultsPhantom's measured doses were reproducible with <3·5% standard deviation between the three TLDs’ repeated measurements. Verification of three head and neck 3D-CRT patients’ plans was implemented, and good agreement between measured values and those predicted by TPS was found. The percentage dose difference for TLD readings matched those corresponding to the calculated dose to within 4%.ConclusionThe good agreement between predicted and measured dose shows that the phantom is a useful and efficient tool for 3D-CRT technique dosimetric verification.

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Pyshkina, M. D., A. V. Vasilyev, A. A. Ekidin, E. I. Nazarov, M. A. Romanova, V. I. Gurinovich, D. I. Komar, and V. A. Kozhemyakin. "Neutron dosimetry at workplaces of JC “Institute of Nuclear Materials”." Radiatsionnaya Gygiena = Radiation Hygiene 14, no. 2 (June 27, 2021): 89–99. http://dx.doi.org/10.21514/1998-426x-2021-14-2-89-99.

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If the neutron fields at personnel workplaces differ from the neutron fields in which individual dosimeters are verified, there is a possibility of additional errors in the assessment of such dosimetric quantities as ambient dose equivalent, individual dose equivalent or effective dose. To take into account the energy distribution of the neutron radiation flux density and the geometry of the irradiation of workers, it is necessary to study the characteristics of the fields of neutron radiation at the workplaces of the personnel. In order to obtain conditionally true levels of personnel exposure to neutron radiation at nuclear facilities, studies of the energy and angular distribution of the neutron radiation flux density were carried out at the workplaces of the Institute of Reactor Materials JSC, Zarechny. The energy distribution of the neutron radiation flux density was obtained using an MKS-AT1117M multi-sphere dosimeter-radiometer with a BDKN-06 detection unit and a set of polyethylene spheres-moderators. The angular distribution of the neutron radiation flux density was estimated from the results of measurements of the accumulated dose of neutron radiation by individual thermoluminescent dosimeters placed on four vertical planes of a heterogeneous human phantom. The results of measurements of the energy and angular distribution of the neutron radiation flux density made it possible to estimate the conditionally true values of the ambient and individual dose equivalents. The calculated conventionally true values differ from the measured values from 0.7 to 8.9 times for the ambient dose equivalent and from 6 to 50 times for the individual dose equivalent. In order to reduce the error in assessing the effective dose of personnel using personal dosimeters, correction factors were determined. For different workplaces and types of personal dosimeters, correction factors are in the range of values from 0.02 to 0.16.

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34

Peng, Jing Yun, Yu Min He, Zheng Ye Xiong, Wen Qing Shi, Yong Qiang Li, and Cun You Huang. "Study on Environmental Materials with the Development of Pure Ultraviolet Irradiator Using Gas Light Source." Advanced Materials Research 703 (June 2013): 106–10. http://dx.doi.org/10.4028/www.scientific.net/amr.703.106.

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This paper has presented a method to get pure ultraviolet rays using Abbe prism, and this principle is used to develop a pure ultraviolet irradiator with a low pressure mercury lamp. We used some thermoluminescent dosimeters (TLDs) Al2O3:C crystals to inspect the irradiating effort of the pure ultraviolet irradiator. This irradiator can be used in environmental radiation dose detector with some TLDs such as Al2O3:C and quartz.

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35

Wong, C. J., T. Ackerly, C. He, W. Patterson, C. E. Powell, G. Qiao, D. H. Solomon, R. Meder, and M. Geso. "Small field size dose-profile measurements using gel dosimeters, gafchromic films and micro-thermoluminescent dosimeters." Radiation Measurements 44, no. 3 (March 2009): 249–56. http://dx.doi.org/10.1016/j.radmeas.2009.03.012.

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36

Angelone, M., P. Batistoni, M. Pillon, V. Rado, and A. Esposito. "Gamma and Neutron Dosimetry Using CaF2:Tm Thermoluminescent Dosimeters for Fusion Reactor Shielding Experiments." Nuclear Science and Engineering 126, no. 2 (June 1997): 176–86. http://dx.doi.org/10.13182/nse97-a24471.

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37

Sherbini, S., J. Sykes, S. W. Porter, and G. Lodde. "Experimental Evaluation of a Method for Performing Personnel Beta Dosimetry Using Multielement Thermoluminescent Dosimeters." Health Physics 49, no. 1 (July 1985): 55–64. http://dx.doi.org/10.1097/00004032-198507000-00005.

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38

Pirchio, R., A. Stefanic, and R. R. Rojas. "CHARACTERISATION OF TLDS-200 AND OSLDS AT LOW X-RAY ENERGIES AND DETERMINATION OF EYE LENS DOSE, THYROID DOSE AND MEAN GLANDULAR DOSE DURING STANDARD MAMMOGRAPHY AND TOMOSYNTHESIS." Radiation Protection Dosimetry 186, no. 4 (April 23, 2019): 469–78. http://dx.doi.org/10.1093/rpd/ncz052.

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Abstract The objective of this study was to characterise thermoluminescent (TLDs) and optically stimulated luminescent dosimeters (OSLDs) at low X-ray energies and estimate the eye lens (DL), thyroid (DT) and mean glandular (DG) doses received during Full-Field Digital Mammography (FFDM) and Digital Breast Tomosynthesis (DBT). The dosimeters were characterised in mammography energies. DL, DT and DG were estimated in FFDM and DBT mode taping dosimeters on the skin of the thyroid gland and on the left eye lens of an Alderson phantom. Dosimeters were also placed on the top of a NORMI PAS phantom simulating a compressed breast. The accuracy, precision and lower limit of detection (LLD) for TLDs and OSLDs were 5 and 8%, 6 and 3%, and 38 and 11 μSv, respectively. The linearity of the kerma response had an R2 > 0.99 and energy dependence was lower than 40%. DT ranged from 0.40 to 2.87 μGy for FFDM and 1.27 to 5.99 μGy for DBT. DG was between 0.50 and 1.27 mGy for FFDM and 1.07 and 1.60 mGy for DBT. DL was below the LLD. Dosimeters showed good performance. DG values were lower than those found in the literature, whereas DT value agreed with references. Differences between DG and DT determined with OSLDs and TLDs were lower than 10% and 200%.

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39

SU, Ling-Nah, Chung-Chieng WU, Pin-Chieh HSU, and Pao-Shan WENG. "Gonadal dose measurement in diagnostic nuclear medicine using thermoluminescent dosimeters." RADIOISOTOPES 34, no. 3 (1985): 137–43. http://dx.doi.org/10.3769/radioisotopes.34.3_137.

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40

Tung, C. J., M. T. Lin, F. Y. Hsu, J. H. Lee, C. H. Chu, and H. Y. Tsai. "Half-value layer determination using thermoluminescent dosimeters for digital mammography." Radiation Measurements 45, no. 3-6 (March 2010): 729–32. http://dx.doi.org/10.1016/j.radmeas.2010.02.015.

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41

Hsu, Pin-Chieh, Pao-Shan Weng, Hsiang-En Wang, and Po-Wen Tseng. "Monitoring Underground Radiation Fields Using Powdered Calcium Sulfate Thermoluminescent Dosimeters." Health Physics 61, no. 3 (September 1991): 367–71. http://dx.doi.org/10.1097/00004032-199109000-00006.

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42

Breen, S. L., and J. J. Battista. "Feasibility of reading LiF thermoluminescent dosimeters by electron spin resonance." Physics in Medicine and Biology 44, no. 8 (July 22, 1999): 2063–69. http://dx.doi.org/10.1088/0031-9155/44/8/315.

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43

Kroutilı́ková, Daniela, Josef Novotný, and Libor Judas. "Thermoluminescent dosimeters (TLD) quality assurance network in the Czech Republic." Radiotherapy and Oncology 66, no. 2 (February 2003): 235–44. http://dx.doi.org/10.1016/s0167-8140(02)00328-6.

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44

Roberson, Peter L., and Fred N. Eichner. "Use of Thin Thermoluminescent Dosimeters for Phantom Surface-Dose Measurements." Health Physics 61, no. 4 (October 1991): 529–33. http://dx.doi.org/10.1097/00004032-199110000-00008.

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45

Friedrich, M., R. Günzel, A. Z. Kiss, E. Koltay, and J. Félszerfalvi. "Bremsstrahlung measurements with collimated thermoluminescent dosimeters around a tandem accelerator." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 234, no. 1 (January 1985): 1–5. http://dx.doi.org/10.1016/0168-9002(85)90801-0.

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46

Santana, Priscila do Carmo, Paulo Marcio Campos de Oliveira, Marcelo Mamede, Mariana de Castro Silveira, Polyanna Aguiar, Raphaela Vila Real, and Teógenes Augusto da Silva. "Ambient radiation levels in positron emission tomography/computed tomography (PET/CT) imaging center." Radiologia Brasileira 48, no. 1 (February 2015): 21–25. http://dx.doi.org/10.1590/0100-3984.2013.1821.

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Objective: To evaluate the level of ambient radiation in a PET/CT center. Materials and Methods: Previously selected and calibrated TLD-100H thermoluminescent dosimeters were utilized to measure room radiation levels. During 32 days, the detectors were placed in several strategically selected points inside the PET/CT center and in adjacent buildings. After the exposure period the dosimeters were collected and processed to determine the radiation level. Results: In none of the points selected for measurements the values exceeded the radiation dose threshold for controlled area (5 mSv/year) or free area (0.5 mSv/year) as recommended by the Brazilian regulations. Conclusion: In the present study the authors demonstrated that the whole shielding system is appropriate and, consequently, the workers are exposed to doses below the threshold established by Brazilian standards, provided the radiation protection standards are followed.

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Almeida, Pedro, Bernard Bendriem, Olivier de Dreuille, Arnaud Peltier, Claudine Perrot, and Vincent Brulon. "Dosimetry of transmission measurements in nuclear medicine: a study using anthropomorphic phantoms and thermoluminescent dosimeters." European Journal of Nuclear Medicine and Molecular Imaging 25, no. 10 (September 29, 1998): 1435–41. http://dx.doi.org/10.1007/s002590050320.

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48

Milković, Đurđica, Vera Garaj-Vrhovac, Mária Ranogajec-Komor, Saveta Miljanić, Goran Gajski, Željka Knežević, and Natko Beck. "Primary DNA Damage Assessed With the Comet Assay and Comparison to the Absorbed Dose of Diagnostic X-rays in Children." International Journal of Toxicology 28, no. 5 (September 2009): 405–16. http://dx.doi.org/10.1177/1091581809344775.

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The aim of this work is to assess DNA damage in peripheral blood lymphocytes of children prior to and following airway X-ray examinations of the chest using the alkaline comet assay and to compare data with the measured absorbed dose. Twenty children with pulmonary diseases, between the ages of 5 and 14 years, are assessed. Absorbed dose measurements are conducted for posterior–anterior projection on the forehead, thyroid gland, gonads, chest, and back. Doses are measured using thermoluminescent and radiophotoluminescent dosimetry systems. Differences between tail lengths, tail intensity, and tail moments as well as for the long-tailed nuclei before and after exposures are statistically significant and are dependent on the individual. The results demonstrate the usefulness of the comet assay as a measure of X-ray damage to lymphocytes in a clinical setting. Doses measured with both dosimeters show satisfactory agreement (0.01 mSv) and are suitable for dosimetric measurements in X-ray diagnostics.

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Wabdan, Ahmed Ali. "Occupational Radiation Exposure to Workers Used18F-FDG." Al-Mustansiriyah Journal of Science 29, no. 4 (May 6, 2019): 100. http://dx.doi.org/10.23851/mjs.v29i4.489.

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The increasing interest of medical institutes in the development of imaging services to include the hybrid system [Positron Emission Tomography combined with Computed Tomography(PET/CT)], this system is acquiring explosive growth due to its ability to accurately detect and stage many types of cancer and follow the progress of treatments. An increasing demand for use of (18F-FDG PET) in oncology has been the main reason for its growth. The physical characteristics of positron emissions result in higher radiation risk for staff and growing use of PET/CT for diagnostic purposes increase radiation exposure. The objective of this study was to estimate the radiation exposure to the medical physicists, technicians and nurses working in three Egyptian nuclear medicine institutes under our investigations, based on the whole body collective dose measured by thermoluminescent dosimeters (TLDs) and the effective dose per study received by medical staff were measured by electronic pocked dosimeters and the finger doses by ring dosimeter during a period of six months. The (mean± SD) dose measured per PET/CT procedure were (2.45±0.137, 3.22±0.218 and 1.69±0.11) μSv for the medical physicist, technician and nurse respectively. The (mean± SD) dose measured per MBq of 18F-FDG were (7.35±0.43, 9.73±0.66 and 5.13±0.33) nSv/MBq for the medical physicist, technician and nurse respectively. The (mean± SD) finger dose measured per 18F-FDGPET/CT scans were (179.9±24.94, 8.82±2.912 and 24.15±4.164) μSv for the medical physicist, technician and nurse respectively.

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Hsu, G. C., H. Y. Tsai, C. H. Chu, and S. M. Yiou. "Energy responses and visibility for thin film-thermoluminescent dosimeters in mammography." Radiation Measurements 43, no. 2-6 (February 2008): 964–67. http://dx.doi.org/10.1016/j.radmeas.2008.01.030.

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