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Journal articles on the topic 'Thermoluminescent dosimeter'

Author: Grafiati

Published: 4 June 2021

Last updated: 7 February 2022

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1

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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2

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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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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4

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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5

Miloichikova, Irina, Sergei Stuchebrov, Gulnur Zhaksybayeva, and Alexander Wagner. "Dosimetry Equipment for the Pulsed X-Ray Source Parameters Investigation." Advanced Materials Research 1084 (January 2015): 121–24. http://dx.doi.org/10.4028/www.scientific.net/amr.1084.121.

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In the article the approbation results of the scintillation dosimeter DRG3-04 of the pulsed X-ray beams and the analysis results of the dosimeter DRG3-04 operational integrity beyond its operating modes are presented. The radiation doses results of the pulsed X-ray generator RAP-160-5 obtained by the solid thermoluminescent detectors DTL-02, the dosimeter-radiometer DKS-96 and the scintillation dosimeter DRG3-04 are demonstrated.

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6

Omanwar, S. K., K. A. Koparkar, and Hardev Singh Virk. "Recent Advances and Opportunities in TLD Materials: A Review." Defect and Diffusion Forum 347 (December 2013): 75–110. http://dx.doi.org/10.4028/www.scientific.net/ddf.347.75.

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Thermoluminescence (TL) is the thermally stimulated emission of light from an insulator or a semiconductor following the previous absorption of energy from ionizing radiation. TL dosimetry is used in many scientific and applied fields such as radiation protection, radiotherapy, industry, and environmental and space research, using many different materials. The basic demands of a thermoluminescent dosimeter (TLD) are good reproducibility, low hygroscopicity, and high sensitivity for very low dose measurements and good response at high doses in radiotherapy and in mixed radiation fields. In this review, we have discussed the past developments and the future opportunities in TLD materials and our efforts to make better future use of low cost materials in TLD applications. For this we have studied and discussed two efficient TLD phosphors with low cost and simple method of preparation on large scale for TLD materials. One of the phosphors is LiF:Mg,Cu,P (LiF: MCP), and another one is LiCaAlF6:Eu, which has the potential to replace conventionally used CaSO4:Dy TL dosimeter. LiF: MCP and LiCaAlF6: Eu phosphors are potential candidates for TL dosimetry and could be good replacement for commercially available phosphors. Apart from this, we have also studied thermoluminescence in Aluminate and Borate materials. We have discussed in detail all three types of TLD materials. First, our study includes complete detail of material properties, methods and dosimetric characterizations of LiF: MCP Phosphor; second, it includes a new TL Dosimeter, LiCaAlF6: Eu and its dosimetric characterizations; and lastly on some TL properties of Li5AlO4: Mn and MgB4O7: Dy,Na. In this review, we discus some recent developments in radiation dosimetry with regards to the measurement techniques and material preparations. Although many materials have been and are currently being studied for TLD, still there is a scope for the improvement in the material properties useful for the TLD, and the synthesis of new, more suitable materials. Contents of Paper

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7

Zivanovic, Milos, Djordje Lazarevic, Olivera Ciraj-Bjelac, Srboljub Stankovic, Sandra Ceklic, and Katarina Karadzic. "Intercomparisons as an important element of quality assurance in metrology of ionising radiation." Nuclear Technology and Radiation Protection 30, no. 3 (2015): 225–31. http://dx.doi.org/10.2298/ntrp1503225z.

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Intercomparisons are important activities performed to ensure that the services provided by calibration laboratories to end-users follow internationally accepted standards. Ionizing radiation dosimetry intercomparisons are usually of two types - postal thermoluminescent dosimeter intercomparisons and ionization chamber calibration intercomparisons. In this paper, both types of intercomparisons are analysed together with the results of seven years of participation in such intercomparisons. Several discrepancies were discovered as a result of intercomparisons analysis and the resolution of the discrepancies was discussed.

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8

Romanyukha, Alexander, Matthew D. Grypp, Thad J. Sharp, John N. DiRito, Martin E. Nelson, Stanley T. Mavrogianis, Jeancarlo Torres, and Luis A. Benevides. "Acceptance Testing of Thermoluminescent Dosimeter Holders." Health Physics 114, no. 5 (May 2018): 543–48. http://dx.doi.org/10.1097/hp.0000000000000845.

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9

Rivera Montalvo, T., C. Furetta, J. Azorín Nieto, C. Falcony Guajardo, M. García, and Eduardo Martínez. "Termoluminescent Properties of High Sensitive ZrO₂+PTFE for UV Radiation Dosimetry." Materials Science Forum 480-481 (March 2005): 373–80. http://dx.doi.org/10.4028/www.scientific.net/msf.480-481.373.

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This paper presents the preparation method, luminescent characteristics and the results of studying the thermoluminescence (TL) properties of zirconium oxide (ZrO2) exposed to 260 nm ultraviolet radiation. The glow curve of ZrO2+PTFE pellets exhibited one peak centered at 180°C about 30°C lower than that the commercially available aluminum oxide peak (Al2O3:C). TL response as a function of spectral irradiance showed good linear in the range from 2.4 to 3000 µJ/cm2 of spectral irradiance. Experimental results of studying the thermoluminescent (TL) properties of ZrO2+PTFE exposed to ultraviolet radiation allow to propose zirconium oxide as an excellent candidate as ultraviolet radiation dosimeter.

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10

Freire de Souza, Luiza, and Divanízia N. Souza. "PRODUÇÃO DE DOSÍMETROS TERMOLUMINESCENTES À BASE DE MgB4O7: Dy e MgB4O7:Tm." Eclética Química Journal 38, no. 1 (October 25, 2017): 101. http://dx.doi.org/10.26850/1678-4618eqj.v38.1.2013.p101-108.

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The thermoluminescent dosimetry (TL) is a well-established technique for the detection of ionizing radiation in hospitals, clinics, and industrial establishments where there is the need to quantify the radiation. For this practice is require the use phosphors which are sensitive to radiation. Some phosphors are already commonly used in this practice, for example, TLD-100 (LiF: Mg, Ti), CaSO4:Tm and CaSO4:Dy. A compound that was most recently introduced in dosimetry and has many advantageous features to detect neutrons, electrons and gamma is the magnesium tetraborate (MgB4O7), but the undoped material is not good for dosimetry, since signal does not show satisfactory thermoluminescence. The present work presents the analysis of the compound MgB4O7 when doped with rare earth elements, thulium (Tm) and dysprosium (Dy). The production of MgB4O7: Dy and MgB4O7: Tm occurred under acidic conditions. Following the process of crystal growth, several tests were made on phosphors produced to verify the quality of materials as TL dosimeter. Initially, was made the identification of the crystalline phases found in the material, using the technique of X-ray diffractometry, and then were evaluated and compared the TL emission curves of the crystals with two different types of dopants, to this, the samples were irradiated with different radiation sources: 137Cs (0,66 MeV), 60Co (1.25 MeV) and X-rays (0.41 MeV) and based on the results was evaluated the energy dependence of phosphors. Another characteristic analyzed, was the decay of TL signal for the material (fading). The results show that the material can be an excellent TL dosimeter when doped with rare earth elements Dy and Tm.

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11

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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12

Ha, Vu Thi Thai, Nguyen Thi Quy Hai, and Nguyen Ngoc Long. "Estimation and Correction for the Temperature Lag in Thermoluminescent Measurements for LiF: Mg, Cu, Na, Si Phosphor." Communications in Physics 21, no. 2 (June 30, 2011): 145. http://dx.doi.org/10.15625/0868-3166/21/2/110.

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In the current work the glow curves for LiF:Mg,Cu,Na,Si thermoluminescent material were measured at various heating rates in the range from 1 K/s to 30 K/s. In the thermoluminescent measurements a contact heating was used to heat the powder samples. The temperature lag between the heating element and the dosimeter was estimated and corrected by applying Kitis-Tuyn's method. Some kinetic parameters of the traps in LiF:Mg,Cu,Na,Si were evaluated using a variable-heating-rate method.

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13

Solomon, S. B., J. R. Peggie, G. Grealy, and V. A. Leach. "An Integrating Thermoluminescent Rn Daughter Personal Dosimeter." Health Physics 52, no. 2 (February 1987): 143–48. http://dx.doi.org/10.1097/00004032-198702000-00002.

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14

Zhao, Nan, Ruijie Yang, and Junjie Wang. "The Dosimetric Property of Tld2000 Thermoluminescent Dosimeter." Brachytherapy 14 (May 2015): S93—S94. http://dx.doi.org/10.1016/j.brachy.2015.02.357.

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15

CANO, A., P. R. GONZÁLEZ, and C. FURETTA. "FURTHER STUDIES OF SOME TL CHARACTERISTICS OF MgB4O7:Dy, Na PHOSPHOR." Modern Physics Letters B 22, no. 21 (August 20, 2008): 1997–2006. http://dx.doi.org/10.1142/s0217984908016674.

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Nowadays, the pacific use of ionizing radiation has attracted a great deal of attention in medicine, as well as in radiodiagnostic, and radiotherapy. However to avoid unnecessary irradiations to the healthy tissue, a strict quality control is required. This has led to the development of a new dosimeter equivalent to the tissue that could be highly suitable for the radiation dosimetry. The borate of magnesium with its low effective atomic number (Z eff ), is considered equivalent to the human-tissue. For this reason, in this work, we present the results obtained of the thermoluminescent characterization of this material. The test that was carried out includes the lower detection limit, sensitivity, reproducibility of the TL measurement, stability of information (fading), and TL response as a function of the delivered dose and energy response, which are recommended by the International Commission on Radiological Units and Measurements (ICRU) and International Commission on Radiological Protection (ICRP). Two different concentrations of Dy activator were used i.e. 1.25 (batch A) and 1.5 (batch B) mol%. Meanwhile, the Na activator was 0.5 mol% in both cases. The results show that this new thermoluminescent material is adequate for radiation dosimetry in different medical applications.

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16

Al-Hinai, Khalid H., Nadjima Benkara Mohd, Nurul Rozullyah Zulkepely, Roslan Md. Nor, Yusoff Mohd. Amin, and D. A. Bradley. "A search for novel thermoluminescent radiation dosimeter media." Applied Radiation and Isotopes 82 (December 2013): 126–29. http://dx.doi.org/10.1016/j.apradiso.2013.07.013.

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17

Dong, Kyung-Rae, Dae Cheol Kweon, Woon-Kwan Chung, Eun-Hoe Goo, Kevin Dieter, and Chong-Hwan Choe. "Study on the angular dependence of personal exposure dosimeter – Focus on thermoluminescent dosimeter and photoluminescent dosimeter." Annals of Nuclear Energy 38, no. 2-3 (February 2011): 383–88. http://dx.doi.org/10.1016/j.anucene.2010.10.003.

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18

Diab, H. M., and R. El-Mallawany. "Estimation of uncertainty for sulfonated grafted low density polyethylene dosimeter using thermoluminescent dosimeter." Measurement 47 (January 2014): 22–25. http://dx.doi.org/10.1016/j.measurement.2013.08.042.

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19

Lah, J., G. Kim, D. Shin, and T. Suh. "SU-GG-T-232: Investigation of Dosimetric Characteristics of Glass Dosimeter and Thermoluminescent Dosimeter for a Mailed Dosimetry." Medical Physics 35, no. 6Part12 (June 2008): 2778. http://dx.doi.org/10.1118/1.2961984.

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20

Maruyama, Daiki, Shin Yanagisawa, Yusuke Koba, Takayuki Andou, and Kiyomitsu Shinsho. "Usefulness of Thermoluminescent Slab Dosimeter for Postal Dosimetry Audit of External Radiotherapy Systems." Sensors and Materials 32, no. 4 (April 20, 2020): 1461. http://dx.doi.org/10.18494/sam.2020.2697.

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21

Salama, Elsayed, and Hala Soliman. "Evaluation of the gamma dose rate inside Egyptian buildings, utilizing theoretical and experimental techniques." Nuclear Technology and Radiation Protection 34, no. 2 (2019): 175–80. http://dx.doi.org/10.2298/ntrp190107019s.

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The indoor low gamma dose rate exposures due to Egyptian room building materials are assessed by means of three different techniques: experimentally by using a thermoluminescent dosimeter, theoretically by using the general room model and by the Monte Carlo simulation through the RESRAD-BUILD software. The present study aims at validating the theoretical methods so that it can be amply used for measuring the low dose rates usually associated with the building materials. The measured in door dose rates were in the range of 55.92 ? 14.47 to 86.89 ? 16.68 nGyh?1 de pending on the position inside the room as obtained by the thermoluminescent dosimeter after 5 months' accumulation. Lower dose rates are obtained near the door and windows while higher dose rates are obtained at the center of the room, and close to the extended walls. Comparable results of the dose rates at same positions inside the room are obtained by the RESRAD-BUILD software. The room model is restricted to the room center and also gives comparable results. The three methods showed comparable results, which in turn confirm the recommendation of using theoretical ones, with RESRAD-BUILD software being more accurate.

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22

Sobotka, Piotr, Bartłomiej Kliś, Zuzanna Baranowska, Katarzyna Wołoszczuk, Katarzyna Rutkowska, and Tomasz Woliński. "Efficient reading of thermoluminescent dosimeter signals using semiconductor detectors." Nukleonika 65, no. 4 (December 1, 2020): 223–27. http://dx.doi.org/10.2478/nuka-2020-0034.

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AbstractThe aim of this experimental work was to examine whether semiconductor photodetectors may be applied for the efficient reading of thermoluminescent dosimeter (TLD) signals. For this purpose, a series of experiments have been performed at the Department of Physics, Warsaw University of Technology, in cooperation with the Central Laboratory for Radiological Protection (CLOR). Specifically, the measurement system proposed here has been designed to detect a signal from TLDs that use a semiconductor detector operating in conditions analogous to those met when using commercial devices equipped with a classic photomultiplier. For the experimental tests, the TLDs were irradiated with a beam of 137Cs radiation in the accredited Laboratory for Calibration of Dosimetric and Radon Instruments. Eventually, a comparison of the results obtained with a semiconductor detector (ID120) and a commercial TLD reader with a photomultiplier tube (RADOS) were made.

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23

Yang, R. "EP-1484: The dosimetric property of TLD2000 thermoluminescent dosimeter." Radiotherapy and Oncology 119 (April 2016): S686. http://dx.doi.org/10.1016/s0167-8140(16)32734-7.

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24

Zhao, N., R. J. Yang, and J. J. Wang. "EP-1405: The dosimetric property of TLD2000 thermoluminescent dosimeter." Radiotherapy and Oncology 115 (April 2015): S758. http://dx.doi.org/10.1016/s0167-8140(15)41397-0.

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25

Kolotilin, V. V., V. I. Hokhrekov, L. M. Tarasova, and S. B. Zakhriapin. "A high sensitivity LiFMg,Cu,P thermoluminescent dosimeter." Nuclear Tracks and Radiation Measurements 21, no. 1 (January 1993): 169–71. http://dx.doi.org/10.1016/1359-0189(93)90071-g.

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26

Silva, Heitor. "The effect of gamma spectrum on thermoluminescent dosimeter response." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 69, no. 2-3 (June 1992): 315–21. http://dx.doi.org/10.1016/0168-583x(92)96024-s.

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27

Leroux, R. "Thermoluminescent dosimeter for the supervision of nuclear power plants." Naturwissenschaften 73, no. 10 (October 1986): 614–15. http://dx.doi.org/10.1007/bf00368773.

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28

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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29

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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Rah, Jeong-Eun, Ju-Young Hong, Gwe-Ya Kim, Yon-Lae Kim, Dong-Oh Shin, and Tae-Suk Suh. "A comparison of the dosimetric characteristics of a glass rod dosimeter and a thermoluminescent dosimeter for mailed dosimeter." Radiation Measurements 44, no. 1 (January 2009): 18–22. http://dx.doi.org/10.1016/j.radmeas.2008.10.010.

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Xiong, Zheng Ye, Ping Ding, Qiang Tang, Jing Min Chen, and Wen Qing Shi. "Thermoluminescence Spectra of Lithium Tetraborate Single Crystal." Advanced Materials Research 160-162 (November 2010): 252–55. http://dx.doi.org/10.4028/www.scientific.net/amr.160-162.252.

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Lithium tetraborate (LBO or LTO) single crystal seems to be a promising new material for thermoluminescent dosimeter (TLD) and SAW resonators. In the present work, thermoluminescence (TL) characteristic and TL spectra of LTO single crystal grown by Bridgman method were measured, the kinetic parameters of TL traps were calculated, and TL spectra were analyzed. The result shows: The primary glow peaks are at about 186oC and 313oC. The activation energies of the traps corresponding to the two TL peaks are 0.96eV and 1.56eV, and the frequency factors are about 7.94×109s-1 and 6.31×1012s-1. The TL spectra of LTO crystal extends from 350nm to 460nm, and has its maximum at about 381nm. The intrinsic luminescent centers can send the energy from crystal lattice to Cu+ ions, because the activation energies of two are quite similar, and the Cu+ ions become new luminescent centers to increase TL sensitivity when Cu ions are doped into LTO crystals.

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32

Dolezal, J. "Radiation exposure of the staff at the therapeutic and diagnostic nuclear medicine department." Nuklearmedizin 47, no. 04 (2008): 175–77. http://dx.doi.org/10.3413/nukmed-0163.

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SummaryAim: To assess a radiation exposure and the quality of radiation protection concerning a nuclear medicine staff at our department as a six-year retrospective study. Therapeutic radionuclides such as 131I, 153Sm, 186Re, 32P, 90Y and diagnostic ones as a 99mTc, 201Tl, 67Ga, 111In were used. Material, method: The effective dose was evaluated in the period of 2001–2006 for nuclear medicine physicians (n = 5), technologists (n = 9) and radiopharmacists (n = 2). A personnel film dosimeter and thermoluminescent ring dosimeter for measuring (1-month periods) the personal dose equivalent Hp(10) and Hp(0,07) were used by nuclear medicine workers. The wearing of dosimeters was obligatory within the framework of a nationwide service for personal dosimetry. The total administered activity of all radionuclides during these six years at our department was 17,779 GBq (99mTc 14 708 GBq, 131I 2490 GBq, others 581 GBq). The administered activity of 99mTc was similar, but the administered activity of 131I in 2006 increased by 200%, as compared with the year 2001. Results: The mean and one standard deviation (SD) of the personal annual effective dose (mSv) for nuclear medicine physicians was 1.9 ± 0.6, 1.8 ± 0.8, 1.2 ± 0.8, 1.4 ± 0.8, 1.3 ± 0.6, 0.8 ± 0.4 and for nuclear medicine technologists was 1.9 ± 0.8, 1.7 ± 1.4, 1.0 ± 1.0, 1.1 ± 1.2, 0.9 ± 0.4 and 0.7 ± 0.2 in 2001, 2002, 2003, 2004, 2005 and 2006, respectively. The mean (n = 2, estimate of SD makes little sense) of the personal annual effective dose (mSv) for radiopharmacists was 3.2, 1.8, 0.6, 1.3, 0.6 and 0.3. Although the administered activity of 131I increased, the mean personal effective dose per year decreased during the six years. Conclusion: In all three professional groups of nuclear medicine workers a decreasing radiation exposure was found, although the administered activity of 131I increased during this six-year period. Our observations suggest successful radiation protection measures at our department.

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33

Stenger, V., M. Osvay, Zs Torday, and Z. Papp. "Electrochemically produced alumina-on-aluminium alloys as thermoluminescent dosimeter for gamma and electron dosimetry." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 299, no. 1-3 (December 1990): 702–7. http://dx.doi.org/10.1016/0168-9002(90)90873-5.

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34

Kumar, Munish, SM Pradhan, RB Rakesh, D. A. R. Babu, AK Bakshi, and Anil Gupta. "Thermoluminescent dosimeter-direct reading dosimeter dose discrepancy: Studies on the role of beta radiation fields." Radiation Protection and Environment 37, no. 3 (2014): 169. http://dx.doi.org/10.4103/0972-0464.154880.

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35

Gastélum, S., E. Cruz-Zaragoza, V. Chernov, R. Meléndrez, M. Pedroza-Montero, and M. Barboza-Flores. "On the use of MWCVD diamond as thermoluminescent gamma dosimeter." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 260, no. 2 (July 2007): 592–98. http://dx.doi.org/10.1016/j.nimb.2007.04.156.

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36

Salehhon, N., S. Hashim, M. K. A. Karim, W. C. Ang, Y. Musa, and N. A. Bahruddin. "128 slice computed tomography dose profile measurement using thermoluminescent dosimeter." Journal of Physics: Conference Series 851 (May 2017): 012002. http://dx.doi.org/10.1088/1742-6596/851/1/012002.

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37

Junot, Danilo O., Max A. Santos, Marcos A. P. Chagas, Marcos A. Couto dos Santos, Luiz A. O. Nunes, and Divanizia N. Souza. "Feasibility study of CaSO4:Tb,Yb as a thermoluminescent dosimeter." Radiation Physics and Chemistry 95 (February 2014): 119–21. http://dx.doi.org/10.1016/j.radphyschem.2013.01.012.

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38

Rojas, S. S., K. Yukimitu, A. S. S. de Camargo, L. A. O. Nunes, and A. C. Hernandes. "Undoped and calcium doped borate glass system for thermoluminescent dosimeter." Journal of Non-Crystalline Solids 352, no. 32-35 (September 2006): 3608–12. http://dx.doi.org/10.1016/j.jnoncrysol.2006.02.128.

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39

Benabdesselam, M., F. Mady, S. Girard, Y. Mebrouk, J. B. Duchez, M. Gaillardin, and P. Paillet. "Performance of Ge-Doped Optical Fiber as a Thermoluminescent Dosimeter." IEEE Transactions on Nuclear Science 60, no. 6 (December 2013): 4251–56. http://dx.doi.org/10.1109/tns.2013.2284289.

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40

Roomi, Sohail, Shahid Ali, Habib Ahmad, Khizar Hayat, Syed Zulfiqar, and Yaseen Iqbal. "Development of a new rare-earth (Dy3+)-based thermoluminescent dosimeter." Journal of Luminescence 196 (April 2018): 373–78. http://dx.doi.org/10.1016/j.jlumin.2017.12.069.

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41

Weng, Pao-Shan, Pin-Chieh Hsu, and Yu-Hsien Chen. "The response of the thermoluminescent dosimeter CaF2: Tm to protons." Applied Radiation and Isotopes 46, no. 10 (October 1995): 1081–83. http://dx.doi.org/10.1016/0969-8043(95)00200-w.

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42

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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43

Geraily, Ghazale, Mohadese Moafi, and AliReza Shirazi. "Comparison of thermoluminescent dosimeter calibration irradiated in gamma knife and60Co instruments." Journal of Cancer Research and Therapeutics 15, no. 8 (2019): 123. http://dx.doi.org/10.4103/jcrt.jcrt_1200_16.

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44

Amit, Gal, and Hanan Datz. "Automatic detection of anomalous thermoluminescent dosimeter glow curves using machine learning." Radiation Measurements 117 (October 2018): 80–85. http://dx.doi.org/10.1016/j.radmeas.2018.07.014.

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Khiem, Do Duy, Hiroto Matsuura, and Masafumi Akiyoshi. "Measurement of dose distribution from a crookes tube using thermoluminescent dosimeter." Radiation Measurements 134 (June 2020): 106312. http://dx.doi.org/10.1016/j.radmeas.2020.106312.

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46

Tsai, W. C., and S. H. Jiang. "A study on annealing technique for Lif:Mg,Cu,P thermoluminescent dosimeter." Radiation Measurements 46, no. 12 (December 2011): 1595–97. http://dx.doi.org/10.1016/j.radmeas.2011.05.024.

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Bakhsh, Muhammad, Wan Saffiey Wan Abdullah, Iskandar Shahrim Mustafa, Muastafa Salih Ali Al Musawi, and Nur Ain Nabilah Razali. "Synthesis, characterisation and dosimetric evaluation of MgB4O7 glass as thermoluminescent dosimeter." Radiation Effects and Defects in Solids 173, no. 5-6 (May 15, 2018): 446–60. http://dx.doi.org/10.1080/10420150.2018.1471080.

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Massillon-JL, Guerda, Conrad S. N. Johnston, and Jorge Kohanoff. "On the role of magnesium in a LiF:Mg,Ti thermoluminescent dosimeter." Journal of Physics: Condensed Matter 31, no. 2 (December 6, 2018): 025502. http://dx.doi.org/10.1088/1361-648x/aaee62.

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Angelone, M., M. Chiti, and A. Esposito. "Measurement of supralinearity factor of CaF2:Tm (TLD-300) thermoluminescent dosimeter." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 117, no. 4 (October 1996): 428–30. http://dx.doi.org/10.1016/0168-583x(96)00340-0.

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Szentmiklósi, L., and Zs Révay. "Characterization of CaSO4-based dosimeter materials with PGAA and thermoluminescent methods." Journal of Radioanalytical and Nuclear Chemistry 267, no. 2 (January 2006): 415–20. http://dx.doi.org/10.1007/s10967-006-0064-2.

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