Статті в журналах: "THERMO LUMINESCENCE DOSIMETER"

1

Hsieh, Chi Wen, and Yi Hong Lin. "Non-Uniform Dose Measurement Based on Two-Stage Bleaching Integrated with Thermo-Luminescence and Optically Stimulated Luminescence Dosimeter." Advanced Materials Research 744 (August 2013): 474–77. http://dx.doi.org/10.4028/www.scientific.net/amr.744.474.

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Thermo luminescence dosimeter and optically stimulated luminescence dosimeter are the most popular dosimeters for personal and environmental radiation monitoring. Basically, these dosimeters are both accumulated dosimeters so that they cannot precisely measure dynamic doses, i.e. there is no any information of time resolving. We developed an algorithm to solve the problem that can depress the uncertain measurement by using partially bleaching techniques; the two-stage bleaching method under the fixed bleaching intensity condition. To analyze and compare the difference of ionizing radiation dose between two dosimeters can partially recall the non-uniformly distributed radiation doses. The Gaussian distribution of dose is considered for the simulation and the results indicated that error of the dose rate could be depressed to 15% compared to the traditional method.

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Sohan, N. A., M. J. Dewan, A. K. M. M. Rahman, M. Al-Mamun, and M. I. Hosan. "Thermo-luminescence Response of Carbon Nanotubes and Some Other Familiar TL Materials Using Medical LINAC." Journal of Scientific Research 12, no. 4 (September 1, 2020): 455–62. http://dx.doi.org/10.3329/jsr.v12i4.45336.

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Strain and impurity defects in carbon nanotubes (CNTs) particularly their potentiality as a new TL material has been studied over the years. In this research, our main objective is to explore the suitability of using CNTs and its composites in the area of TL dosimeter. For this purpose, a study was carried out between the TL responses of the dosimeters TLD-100, TLD-7000 and NaI-LiF pellets. To carry out this research, equivalent irradiations were performed with these pellets using clinical linear accelerator (LINAC) under 6 MV X-ray photon beam. The dose range was from 0.5 to 5 Gy. During irradiation, the dose rate was kept constant at 300 MU/min. TLD reader was used to readout the samples in a flowing N2 atmosphere to reduce surface oxidation.During readout, pre-heat temperature was set initially at 50 °C, acquired temperature rate 10 °C/s and maximum annealed temperature was 300 °C. Response of TLD-100 under varying dose was typically linear for any doses but other dosimeters TLD-7000 showed supra-linearity beyond 2 Gy and NaI-LiF pellets showed sub-linearity response after 2 Gy. The TL glow peak of CNTs indicated that it was lying somewhere away from 300 °C.

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Omer, Mohammed A. Ali, Abdulrahman A. Alsayyari, Jumaa Y. Tamboul, Rowida B. Ali, Amira A. Ahmed, and Ahmed Abukonna. "Studying of Common Factors Affecting Reading of Lithium Fluoride Thermo-Luminescence Dosimeter Crystal." Open Journal of Biophysics 07, no. 01 (2017): 14–24. http://dx.doi.org/10.4236/ojbiphy.2017.71002.

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4

Noble, Brooklyn, Dong-Ok Choe, and Tatjana Jevremovic. "Experimental and MCNP5 based evaluation of neutron and gamma flux in the irradiation ports of the University of Utah research reactor." Nuclear Technology and Radiation Protection 27, no. 3 (2012): 222–28. http://dx.doi.org/10.2298/ntrp1203222n.

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Neutron and gamma flux environment of various irradiation ports in the University of Utah training, research, isotope production, general atomics reactor were experimentally assessed and fully modeled using the MCNP5 code. The experimental measurements were based on the cadmium ratio in the irradiation ports of the reactor, flux profiling using nickel wire, and gamma dose measurements using thermo luminescence dosimeter. Full 3-D MCNP5 reactor model was developed to obtain the neutron flux distributions of the entire reactor core and to compare it with the measured flux focusing at the irradiation ports. Integration of all these analysis provided the updated comprehensive neutron-gamma flux maps of the existing irradiation facilities of the University of Utah TRIGA reactor.

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5

Nurdin, W. B., Aswad, and K. Bariah. "Effect of SSD and absorbing filter in calibration process of Thermo Luminescence Dosimeter TLD-700." Journal of Physics: Conference Series 1341 (October 2019): 082029. http://dx.doi.org/10.1088/1742-6596/1341/8/082029.

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6

Hegazy, Ehab A. "Comparison Between Thermo Luminescence Dosimeter and Planning System Dose Calculation in The Brain and Spinal Cord Tumour." JOURNAL OF ADVANCES IN PHYSICS 16, no. 1 (August 7, 2019): 272–79. http://dx.doi.org/10.24297/jap.v16i1.8375.

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Radiotherapy of Spinal cord and brain tumor requires High care due to considerable changes in the white matter of the brain, which consequently lead to a reduction of patient learning and mental skills. It is considered a very critical tumor due to high sensitivity of gross volume location and normal tissues surrounding it, including eye, heart, plate thyroid, and testis. XiO planning systems, TLD dosimeter found in Mansoura university oncology department, CMS XIO USA TPS were compared using electron and photon beams with different energies at a different site in target volume and organs at risk. We conclude that regular calibration of planning systems and direct measurement of the dose delivered to main target and organs at risk should be done to avoid the difference between XiO planning systems and direct measurement by TLd.

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7

Sneha, C., SureshM Pradhan, Kshama Srivastava, and Ratna Pradeep. "Response of CaSO4:Dy based thermo luminescence dosimeter badge to137Cs and60Co radiations and its implications on estimation of personal dose equivalent." Radiation Protection and Environment 39, no. 2 (2016): 91. http://dx.doi.org/10.4103/0972-0464.190392.

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8

Kurrey, Manmohan Singh, and Bhoopendra Dhar Diwan. "Synthesis and Characterization of Novel ZnO Nanophosphors." Advanced Materials Research 938 (June 2014): 145–48. http://dx.doi.org/10.4028/www.scientific.net/amr.938.145.

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In this paper, the novel ZnO nanophosphors is synthesized by solgel method. The study exposed ZnO nanophosphors samples in Gamma (y) radiation to investigate their thermo-luminescence (TL) intensity as a function of temperature. The thermo-luminescence response has been studied in the dose range 0.291.16 kGy and it is observed that the thermo-luminescence response increases with increase in the dose. Moreover, the TL intensity increases with temperature and attains its maximum value near 200 Cand decreases after this temperature. Keywords: Dosimetry; Thermo-luminescence; Zinc oxide; Nanophosphors.

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9

Kurrey, Manmohan Singh, and Bhoopendra Dhar Diwan. "Photo-Luminescence Properties of Novel ZnO Nano-Phosphors." Advanced Materials Research 938 (June 2014): 311–15. http://dx.doi.org/10.4028/www.scientific.net/amr.938.311.

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In this paper we have reported excellent luminescence properties of novel nanophosphors synthesized through solgel method with narrow size distribution. The size and morphology of the prepared ZnO nanophosphors has been confirmed through XRD and SEM. We have investigated their photo-luminescence (PL) intensity as a function of wavelength. We have prepared ZnO nanophosphor of size 6 nm. It is observed two different emission peaks near 375 nm in the ultraviolet (UV) and near 525 nm in the visible region. The prepared ZnO nanophosphor has enough potential for optoelectronic applications. Keywords: Dosimetry; Thermo-luminescence; Zinc oxide; Nanophosphors.

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10

Saroja, R. Ragel Mabel. "ASSESSMENT OF INDOOR RADIATION DOSE RECEIVED BY THE RESIDENTS OF NATURAL HIGH BACKGROUND RADIATION AREAS OF COASTAL VILLAGES OF KANYAKUMARI DISTRICT, TAMIL NADU, INDIA." Green Chemistry & Technology Letters 1, no. 01 (November 1, 2015): 01–05. http://dx.doi.org/10.18510/gctl.2015.111.

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Radiation exposure and effective dose received through two routes of exposure, viz. external and internal, via inhalation, by residents of coastal villages belonging to Natural High Background Radiation Areas (NHBRA) of Kanyakumari District and Tamil Nadu inIndiawere studied. While the indoor gamma radiation levels were monitored using Thermo Luminescent Dosimeters (TLDs), the indoor radon and thoron gas concentrations were measured using twin chamber dosimeters employing Solid State Nuclear Track Detectors (SSNTDs, LR-115-II). The average total annual effective dose was estimated and found to be varied from 2.37 to8.64 mSv.

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11

Zacharias, N., M. Stuhec, Z. Knezevic, E. Fountoukidis, C. T. Michael, and Y. Bassiakos. "Low-dose environmental dosimetry using Thermo- and Optically Stimulated Luminescence." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 580, no. 1 (September 2007): 698–701. http://dx.doi.org/10.1016/j.nima.2007.05.125.

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12

Wang, Fengdie, Zhonghai Wang, Yuchi Wu, Shaoyi Wang, Yonghong Yan, Minghai Yu, Xiaohui Zhang, et al. "An active dose-measuring device for X-rays generated by ultra-short, ultra-intense laser pulses." Journal of Instrumentation 18, no. 03 (March 1, 2023): P03005. http://dx.doi.org/10.1088/1748-0221/18/03/p03005.

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Abstract Ultra-short, ultra-intense laser pulses can create extreme physical conditions for a wide range of applications in atomic and molecular physics, materials chemistry, and inertial-confinement fusion. However, laser-matter interactions can be accompanied by significant X-ray emission that introduces radiation risks to the nearby environment and personnel. It is usually to monitor the radiation dose during in high-intensity laser-target interactions with optically stimulated luminescence and thermo-luminescence devices. However, these passive methods cannot measure the radiation dose in real time, while most active dosimeters cannot accurately measure pulsed radiation doses. Here, transient pulse X-ray radiation doses are converted by CdWO4 crystals into slow signals. Because the crystals have a 14-μs luminescence decay time, they can absorb sub-nanosecond X-ray pulses and release the energy at a 100-μs rate, thus reducing the linear-response pressure of subsequent devices. A pulse detector based on a CdWO4 crystal, a phototube, and a custom signal-processing circuit was developed. Experiments were performed at the 45-TW femtosecond laser facility of the Laser Fusion Research Center. The detector deviation was less than ±20% relative to that of an ionization-chamber detector. This initially verified its feasibility for real-time pulsed X-ray radiation detection.

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13

Soliman, C., and M. A. Hussein. "Some thermo-stimulated luminescence parameters of quartz arenite relevant to gamma dosimetry." Radiation Effects and Defects in Solids 165, no. 3 (March 2010): 245–51. http://dx.doi.org/10.1080/10420150903449704.

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14

Yuen, P., L. J. Brewster Mallalieu, and R. Sharma. "Comparison of Optically Stimulated Luminescence Detectors with Thermo Luminescence Detectors for In Vivo Dosimetry of Pediatric Total Body Irradiation Patients." International Journal of Radiation Oncology*Biology*Physics 81, no. 2 (October 2011): S664—S665. http://dx.doi.org/10.1016/j.ijrobp.2011.06.1947.

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15

Fuller, C. D., C. R. Thomas, A. Wong, L. Voeltz, B. J. Salter, and M. Fuss. "Thermo-luminescent dosimeter evaluation of extra-target dose in intensity modulated sequential tomotherapy for pancreatic cancer." Journal of Radiotherapy in Practice 5, no. 3 (September 2006): 173–76. http://dx.doi.org/10.1017/s1460396906000239.

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The proximity of abdominal tumors to non-target organs has motivated exploration of intensity modulated radiation therapy (IMRT), with its demonstrated capability to create conformal dose gradients, in abdominal tumors. However, substantial extra-target dose may be observed to radiosensitive organs remote from the treatment field.We present dosimetric data from two patients receiving abdominal IMRT using a sequential tomotherapy technique, demonstrating substantial dose to extra-target organs.

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16

Sadeghi, Nahid, and Rohollah Ahangari. "Radiological Assessment of Atmospheric Release from Tehran Research Reactor during Normal Operation by Using Pc-Cream Code." International Letters of Natural Sciences 54 (May 2016): 17–26. http://dx.doi.org/10.18052/www.scipress.com/ilns.54.17.

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In this work, radiological assessment of atmospheric release from Tehran’s Research Reactor (TRR) stack and assessment of public exposures under normal operation has been studied. To perform tasks mentioned above, Pc-Cream computer code which simulates Gaussian Dispersion air transport plume model as well as laboratory analysis of the soil and leaves samples and TLD (Thermo Luminescent Dosimeter) monitoring around the TRR site was used. Results of the Pc-Cream code showed that the annual committed and external dose received by the individual in the vicinity of the reactor is below the regulatory limit. Also, the results of laboratory analysis of available radionuclides in the soil and leaves samples showed that the concentrations are close to the background (K40=635, Th232=28, Cs137=0.29 up to 28.82, Ra226=25 (Bq[1]/Kg) in soil and K40=457, Be7≈70 (Bq/Kg) in leaves) and confirm the code results. The monitored dose values of the TLD detectors were positioned around the reactor within 500 m radius shows that the background dose in vicinity of TRR (113 μSv up to 150 μSv) is consistent with the background dose in Tehran province (125 μSv).

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17

Sadeghi, Nahid, and Rohollah Ahangari. "Radiological Assessment of Atmospheric Release from Tehran Research Reactor during Normal Operation by Using Pc-Cream Code." International Letters of Natural Sciences 54 (May 11, 2016): 17–26. http://dx.doi.org/10.56431/p-n778vb.

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In this work, radiological assessment of atmospheric release from Tehran’s Research Reactor (TRR) stack and assessment of public exposures under normal operation has been studied. To perform tasks mentioned above, Pc-Cream computer code which simulates Gaussian Dispersion air transport plume model as well as laboratory analysis of the soil and leaves samples and TLD (Thermo Luminescent Dosimeter) monitoring around the TRR site was used. Results of the Pc-Cream code showed that the annual committed and external dose received by the individual in the vicinity of the reactor is below the regulatory limit. Also, the results of laboratory analysis of available radionuclides in the soil and leaves samples showed that the concentrations are close to the background (K40=635, Th232=28, Cs137=0.29 up to 28.82, Ra226=25 (Bq[1]/Kg) in soil and K40=457, Be7≈70 (Bq/Kg) in leaves) and confirm the code results. The monitored dose values of the TLD detectors were positioned around the reactor within 500 m radius shows that the background dose in vicinity of TRR (113 μSv up to 150 μSv) is consistent with the background dose in Tehran province (125 μSv).

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18

Acharya, Prabhash, Gita Chalise, Bipin Rijal, Hari Prasad Lamichhane, and Buddha Ram Shah. "Study on Occupational Radiation Exposure at Different Hospitals in Nepal using ThermoluminescenceDosimetry." Nepal Journal of Science and Technology 19, no. 1 (July 1, 2020): 180–85. http://dx.doi.org/10.3126/njst.v19i1.29799.

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The clinical efficacy of using ionizing radiation in diagnosis and treatment of diseases has been revolutionized, benefitting humankind and, at the same time, imposing deleterious health effects, if not handled carefully. Personnel dosimetry has emerged as an essential tool to monitor occupational radiation exposure. The present study intends to reveal and describe the scenario of occupationally exposed staff by assessing an individual’s dose in radiological facilities at different hospitals in Nepal. Thermo luminescent Dosimetry (TLD) has been used for assessing individual doses. Altogether eight hospitals were chosen from different locations of Nepal. TLD badges were worn by the radiation workers on their chest level while working with the radiological equipment for about three to ten months during their routine work. Later the badges were read out in the TLD badge reader system available at Nepal Academy of Science and Technology (NAST) to obtain the exposed doses. CaSO4: Dy was used as TL phosphor. Exposed doses for health personnel during their routine work were founding the range of (2.21 to 16.17) 0.01 mSv per year, which was low compared to the permissible dose limit of 20 mSv per year set up by International Commission on Radiological Protection(ICRP). Although the exposed dose rates in the monitored hospitals are below the recommended dose limits, it should be made as low as possible based on the ALARA principle.

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19

Roberge, David, William Parker, Tamim M. Niazi, and Marina Olivares. "Treating the Contents and Not the Container: Dosimetric Study of Hair-sparing Whole Brain Intensity Modulated Radiation Therapy." Technology in Cancer Research & Treatment 4, no. 5 (October 2005): 567–70. http://dx.doi.org/10.1177/153303460500400510.

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Hematogenous metastatases are the most common adult central nervous system malignancies. The standard treatment of these patients continues to include whole brain radiation. An unavoidable toxicity of this treatment is acute iatrogenic alopecia. This alopecia is a significant cause of patient distress. Our purpose was to quantify the sparing of the hair bearing skin that could be achieved by using a complex hair-sparing approach. To achieve this goal, we treat an anthropomorphic phantom with both conventional and inverse-planned intensity-modulated portals. The skin dose was evaluated through dose-volume histograms and thermo-luminescent dosimetry. The median calculated dose was reduced by 38%. The average measured dose at five surface points was reduced by 53% — from 95% of the prescription dose with the conventional plan, to 44%, with the IMRT plan. This sparing was achieved while maintaining adequate target coverage. Because of the low radiation tolerance of the hair follicle, this dose reduction is not expected, on its own, to eliminate radiation alopecia but bears promise in combination with other toxicity-sparing strategies.

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20

Gruel, A., K. Ambrožič, C. Destouches, V. Radulović, A. Sardet, and L. Snoj. "Gamma-heating and gamma flux measurements in the JSI TRIGA reactor, results and prospects." EPJ Web of Conferences 225 (2020): 04029. http://dx.doi.org/10.1051/epjconf/202022504029.

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The neutron field of various irradiation positions of the TRIGA Mark II reactor of the Jožef Stefan Institute has been thoroughly characterized by neutron activation dosimetry and miniature fission chambers techniques. In order to have a fully validated calculation scheme to analyze and plan experiments, the gamma field also has to be experimentally validated. The 10-year long collaboration between CEA and JSI is a perfect framework to carry out such a study, and measurements of the gamma field started in late 2016. Several measurement techniques were investigated in in-core and ex-core positions. On-line measurements were carried out using miniature ionization chambers manufactured by the CEA and PTW Farmer ionization chambers. Positional dependence was studied, showing a decrease in the delayed gamma contribution to the total gamma flux with increasing distance from the reactor core center. To characterize the gamma dose in the core, as well as in the periphery, thermo- and optically stimulated luminescent detectors were tested. These detectors are commonly used at CEA to measure the gamma dose in a given material in order to study the nuclear heating in various core elements (control rod, baffle, structural material). Different filters were used in order to assess an integrated dose ranging from a few Gy up to several kGy. The feasibility of such measurements demonstrates the complementarity between measurements with dosimetry and ionization chambers from low to very high gamma-dose environment, such as in material testing reactors.

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21

Khanal, Suraj, Zoubir Ouhib, Rashmi Benda, and Theodora Leventouri. "Evaluation of surface dose outside the treatment area for five breast cancer irradiation modalities using thermo-luminescent dosimeters." International Journal of Cancer Therapy and Oncology 3, no. 1 (February 5, 2015): 030117. http://dx.doi.org/10.14319/ijcto.0301.17.

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22

Shoshtary, Akram, Jalil Pirayesh Islamian, Mohsen Asadinezhad, and Alireza Sadremomtaz. "An Evaluation of the Organ Dose Received by Cardiologists Arising From Angiography Examinations in Educational Hospital in Rasht." Global Journal of Health Science 8, no. 7 (November 18, 2015): 185. http://dx.doi.org/10.5539/gjhs.v8n7p185.

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<p>Interventional procedures, cine acquisitions and operation of fluoroscopic equipment in high-dose fluoroscopic modes, involve long fluoroscopic times which can lead to high staff doses. Also, Coronary angiography (CA) procedures require the cardiologist and assisting personnel to remain close to the patient, which is the main source of scattered radiation. Thus, radiation exposure is a significant concern for radiation workers and it is important to measure the radiation doses received by personnel and evaluate the parameters concerning total radiation burden. In this research, we investigated radiation doses to 10 cardiologists performing 120 CA procedures. Using thermo luminescent dosimeters doses to the wrists, thyroid and eyes per procedure were measured. Based on the measured dose values, maximum doses to the Left wrist, Right wrist, thyroid and eyes of cardiologist were measured 241.45 µSv, 203.17 µSv, 78.21 µSv and 44.58 µSv, respectively. The results of this study indicate that distance from the source, use of protective equipment's, procedure complexity, equipment performance, and cardiologist experience are the principal exposure-determining variables. It can be conclude that if adequate radiation protection approaches have been implemented, occupational dose levels to cardiologists would be within the regulated acceptable dose limits.</p>

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23

Usman Sani, Bashir Gide Muhammad, Dimas Skam Joseph, and D. Z. Joseph. "EVALUATION OF OCCUPATIONAL RADIATION EXPOSURE IN A RADIO-DIAGNOSTIC FACILITY IN KATSINA- NIGERIA." FUDMA JOURNAL OF SCIENCES 4, no. 2 (October 7, 2020): 722–29. http://dx.doi.org/10.33003/fjs-2020-0402-406.

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Poor implementation of quality assurance programs in the radiation industry has been a major setback in our locality. Several studies revealed that occupational workers are exposed to many potential hazards of ionizing radiation during radio-diagnostic procedures, yet radiation workers are often not monitored. This study aims to evaluate the occupational exposure of the radiation workers in Federal Medical Centre Katsina, and to compare the exposure with recommended occupational radiation dose limits. The quarterly readings of 20 thermo-luminescent dosimeters (TLDs') used by the radiation workers from January to December, 2019 were collected from the facility's radiation monitoring archive, and subsequently assessed and analyzed. The results indicate that the average annual equivalent dose per occupational worker range from 0.74 to 1.20 mSv and 1.28 to 2.21 mSv for skin surface and deep skin dose, measured at 10 mm and 0.07 mm tissue depth respectively. The occupational dose was within the recommended national and international limits of 5 mSv per annum or an average of 20 mSv in 5 years. Therefore, there was no significant radiation exposure to all the occupational workers in the study area. Though, the occupational radiation dose is within recommended limit, this does not eliminate stochastic effect of radiation. The study recommended that the occupational workers should adhere and strictly comply with the principles of radiation protection which includes distance, short exposure time, shielding and proper monitoring of dose limits. Furthermore, continuous training of the radiation workers is advised.

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Chukhray, Nataliya, and Oleksandra Mrykhina. "Technology assessment to transfer them from an engineering university to a business environment." Problems and Perspectives in Management 17, no. 4 (January 9, 2020): 504–16. http://dx.doi.org/10.21511/ppm.17(4).2019.41.

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Technology transfer from universities to the business environment plays a key role in use of the open innovation concept. Meanwhile, in Ukraine which has a sufficiently high level of scientific and technological capacity, universities do not fully respond to market demands and do not receive the proper commercial results. One of the reasons for this is that current methods and models do not allow justifying the level of techno&shy;logy transferability. This article aims to present a methodological approach to assessing the transferability of technologies from universities to the business environment and to develop a method for determining the integral index of technology transferability. Therefore, the study considered and substantiated options for this transfer based on the sale of technology licenses by the universities; creation of spin-off companies by the university; technology transfer as startups; conclusion of a joint activity agreements; scientific and technical cooperation. A market technology launch matrix was developed to select these models. The developed methodological tools can be used to compare investment projects. The results obtained were tested based on technology of personal passive optically stimulated luminescence dosimetry of ionizing radiation.

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25

Khakimova, Nodira U., Elena Yu Malysheva, Shoira G. Shosafarova, and Ulmas M. Mirsaidov. "Comparative analysis of the external exposure of different professional groups of medical staff of Dushanbe city of the Republic of Tajikistan." Radiatsionnaya Gygiena = Radiation Hygiene 12, no. 4 (January 7, 2020): 78–81. http://dx.doi.org/10.21514/1998-426x-2019-12-4-78-81.

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The work provides a comparative analysis of average annual individual radiation doses based on the obtained values of individual dose equivalent Hp (10), which had been obtained during 5 years of investigations (2014-2018) by using the thermo-luminescent dosimetry method of 70 employees working computed tomography, radioscopy, fluorography and radiography from 15 medical institutions in Dushanbe city. The ratio of medical personnel of the different professional groups showed that 63% of them were engaged in radiography, 19% x-ray, 10% computed tomography and 8% radioscopy. Analysis of the average annual radiation doses of every occupational group showed that the specialists in charge of fluorography have a high dose (max 1.74 mSv) and the personal of computed tomography have the lowest dose (max 1.34 mSv), and over time there is a tendency to equalize the values of average annual doses for all professional groups in the area close to the value of 1.5 mSv. The obtained data of the effective annual dose for all occupational categories had not exceeded the permissible dose limits values required by the «Radiation Safety Standards» (NRB-06 SP 2.6.1.001-06). Calculations are given without subtracting background values. The analysis data allows to identify the most exposed professional groups and to address the issues of ensuring radiation safety in a targeted manner.

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Nouet, P., G. Dipasquale, A. Dubouloz, and M. Rouzaud. "Planning, treatment and in vivo thermo-luminescent dosimetry in patients with breast cancer treated with a VMAT technique: Geneva experience." Physica Medica 29 (June 2013): e32. http://dx.doi.org/10.1016/j.ejmp.2013.08.101.

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27

Haq, M. Mohib-ul, Ghulam Mohammad Mir, Nazir Ahmad Khan, Mohammad Ashraf Teli, M. Maqbool Lone, Fir Afroz, Shoukat H. Khan, Tanveer A. Rather, and Aijaz Ahmad Khan. "Study of Radiation Safety Concerns in Departments of Diagnostic Radiology of various Hospitals of Kashmir valley." JMS SKIMS 13, no. 2 (December 17, 2010): 51–55. http://dx.doi.org/10.33883/jms.v13i2.48.

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BACKGROUND: A primary consideration in any radiographic procedure is to reduce the dose to the patient and the operator while still achieving the diagnostic goals. OBJECTIVE: To study the radiation exposure and protective measures in different units of various hospitals in Kashmir valley in compliance to recommendations from regulatory authorities. METHODS: Twenty-eight stationary X-ray units of various major hospitals of the Kashmir Valley were surveyed by the radiation safety group of SKIMS. Panoramic survey meter, Thyac-V survey meter-470A, Prima-7 digital survey meters were used for radiation exposure estimations. The radiation level measurements were carried out at different critical locations like control console, door and the corridor adjacent to the Diagnostic equipment and were compared with the standards of AERB and IAEA. RESULTS: Of the 28 stationary X-Ray units identified 21 were functional and surveyed. Seventy seven Radiation workers (Technicians) operating these units perform about 1335 diagnostic procedures daily on these units. Out of 21 X-ray units surveyed, 9 (42.86%) had dose rate at the control panel within the permissible limits and 12(57.14%) had exposure levels higher than permissible limits. The dose levels at the door and corridor were exceeding the permissible limits in all the units. Most of the radiation workers had no concept of radiation protective measures and did not use any personal radiation monitoring device like TLD (Thermo-luminescent dosimeter). CONCLUSIONS: To avoid radiation exposure, the radiation safety measures ought to be strictly followed which is possible by making the concerned authorities answerable and accountable. Also the radiation workers need to be made aware of hazards of radiation exposure, importance of using personnel monitoring devices and providing knowledge about the safety measures. (JMS 2010;13(2):51-55)

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Kennedy, Patrick J., Lei Wang, Michael J. Burke, Glenn Sullivan, Jose M. Hernandez, and William T. Tse. "Irradiation Conditions Necessary for Murine Bone Marrow Ablation Utilizing an X-Ray-Based Irradiator." Blood 104, no. 11 (November 16, 2004): 4959. http://dx.doi.org/10.1182/blood.v104.11.4959.4959.

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Abstract In mouse models of bone marrow transplantation, irradiation of recipient animals to ablate endogenous hematopoietic tissues is conventionally given by radioisotope-based irradiators. Recently, cabinet-size, X-ray-based irradiators have been advertised as a safe and cost-effective alternative source of radiation. Whereas 137Cesium-generated gamma-rays have an energy of 662 kV, X-rays generated from cabinet irradiators typically have a peak energy of only 130 kV, thus potentially limiting their ability to penetrate tissues. In this study, we performed dosimetry studies of a Faxitron RX650 irradiator operating at peak voltage and tested its effectiveness in ablating murine bone marrow. Thermo-luminescence dosimetry (TLD) chips were placed on and under the skin of freshly sacrificed mice or embedded in the tissue next to the pelvis and long bones. The mice were placed inside a Plexiglas cage at a distance of 16 inches from the X-ray tube and irradiated in a fashion that simulated live mouse irradiation. The TLD chips recorded radiation doses of 150 cGy/min to the skin, 73 cGy/min to the pelvis and 47 cGy/min to the femur, which were dramatically lower than the nominal dose of 527 cGy/min suggested by the manufacturer. This result demonstrated that there was a marked attenuation of radiation by intervening materials and a significant difference in doses delivered to superficial and deep tissues of irradiated mice. Preliminary studies performed on live mice showed that irradiation at a dose high enough to ablate bone marrow cells caused extensive ulceration of back skin, necrosis of ear cartilage and increased mortality rates post-irradiation. To overcome these problems, a 4-point-rotation irradiation procedure was subsequently adopted, whereby the mice to be irradiated were first anesthetized and then placed inside a confinement cage to receive equal fractions of radiation in the supine, prone, left lateral decubitus and right lateral decubitus positions, with four hours between the first and last two fractions. Dosimetry analysis showed that this irradiation protocol gave an effective average dose of 55 cGy/min to hematopoietic tissues of the irradiated mice. To confirm the biological validity of this protocol, four cohorts of mice were given effective doses of either 200, 600, 900 or 1100 cGy and then transplanted with 80,000 bone marrow cells. Twelve days later, prominent spleen colonies (CFU-S) derived from transplanted hematopoietic progenitors were seen in the 900 and 1100 cGy cohorts, whereas no colonies were observed in the 200 and 600 cGy cohorts, indicating successful endogenous bone marrow ablation using the higher radiation doses. Engraftment studies were then performed in which four cohorts of C57BL/6 (B6) mice were given effective doses of either 200, 600, 900 or 1100 cGy, respectively, and transplanted with 5x106 B6.SJL bone marrow cells per mouse. After four weeks, peripheral blood analysis showed donor engraftment rates of <10% in mice irradiated with 200 or 600 cGy but >90% in mice irradiated with 900 or 1100 cGy. Our studies showed that X-ray-based irradiators can be used effectively for bone marrow ablation in mice, but careful dosimetry calibration and a 4-point-rotation irradiation procedure is necessary to prevent radiation-associated tissue damage.

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Gruel, A., D. Fourmentel, C. El Younoussi, B. El Bakkari, Y. Boulaich, B. Nacir, and A. Lyoussi. "Characterization of the gamma flux in a tangential channel of the CENM TRIGA MARK II research reactor." EPJ Web of Conferences 225 (2020): 04030. http://dx.doi.org/10.1051/epjconf/202022504030.

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The CNESTEN (National Center for Energy Sciences and Nuclear Technology, Morocco) operates a TRIGA Mark II reactor, which can reach a thermal maximum power at steady state of 2 MW. In reactors devoted to research and experiments, it is mandatory to characterize the neutron and photon fields in the irradiation positions. Together with a computational model of the core, it ensures the ability to reach the requested uncertainties when performing experiments, such as detectors testing, irradiation for hardening or nuclear data measurements. The neutron field of different irradiation positions has been characterized by dosimetry techniques and compared to the MCNP full model of the reactor. Preliminary photon propagation calculations are also performed with this model, but up to now, no experimental validation of the results exists. The aim of the newly set collaboration between CEA and CNESTEN is to characterize the gamma field of these positions. The first position investigated is the part of the NB1 tangential channel closest to the core. Among gamma measurements techniques, and according to the constraints arising from using this channel, it was chosen to use thermos- and optically stimulated luminescent detectors. This paper presents the experiments carried out in September 2018 as well as their results. Three detectors types were used: TLD400 (CaF2:Mn), TLD700 (7LiF:Mg,Ti) and OSLD (Al2O3:C). Measurements were performed in several steps: background measurements, transient measurements (divergence phase + SCRAM), and irradiation at steady state. In the end, these measurements will provide a dose as well as a gamma flux value for this position.

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30

Hui, Susanta, Yutaka Takahashi, Shernan G. Holtan, Rezvan Azimi, Masashi Yagi, Jessie Ingvalson, Davis Seelig, et al. "Comparison of Oxidant Stress and Damage-Related Responses after Total Body Irradiation Versus Total Marrow Irradiation in Rodents." Blood 124, no. 21 (December 6, 2014): 3804. http://dx.doi.org/10.1182/blood.v124.21.3804.3804.

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Abstract Background: Total body irradiation (TBI) is an important component of many hematopoietic cell transplantation (HCT) preparative regimens because of its efficacy in immune suppression and leukemia eradication. However, TBI is also associated with risk of damage to vital organs, especially the gastrointestinal tract and lungs, which can lead to several early and late complications. We hypothesized that total marrow irradiation (TMI) would induce fewer damaging side effects, especially in aging mice, but similar marrow response compared to TBI. To test this hypothesis, we developed a mouse model of TMI and compared its effects with TBI and untreated control mice. Materials and Methods: We compared two types of 8.5 Gy radiation exposures – TBI and TMI in adult (4 months, N=8) and aging (26 months, N=8) BALB/c mice to age matched non-irradiated control mice (N=8) to determine physiologic differences 2 days post irradiation. In TMI mice, viscera and cranium were shielded using a copper compensator (Figure 1a). Organ dosimetry was verified using thermo luminescent dosimeters and GafChromic film. Pulmonary function testing was performed on day 2, followed by sacrifice and collection of serum, lungs, gastrointestinal (GI) tissue, and marrow for further testing. Changes in organ histology were determined by microscopy and immunohistochemistry. Differences in oxidative stress in the GI tract were examined by measurement of reduced glutathione (GSH) to oxidized glutathione (GSSG) ratio by ELISA. The profile of cytokines, chemokines, and damage-related proteins (TNFa, IFNg, IL-1b, IL-6, IL-10, IL-12p70, SDF-1a, MCP-1/JE, GRO/CXCL1/KC, MMP2, MMP9, MMP12, and 8-isoprostane) in serum, the lung, and bone marrow were determined via magnetic bead array or ELISA. Results: The radiation dosage delivered to the marrow was the same in TBI and TMI, although critical organ dosage in TMI was reduced by 35-50%. Marrow histologic analysis of both groups revealed similar effects on the myeloid, erythroid, and megakaryocyte series and similar proliferative response by Ki67 staining (Figure 1b, 1c). Levels of IL-10 and SDF-1a were increased in the marrow of mice receiving TBI and TMI compared to controls, whereas mice receiving TMI had elevated marrow levels of MMP9 (Figure 1d). Recipients of TBI showed worse GI pathology, as evident by diminished median crypt depth and villous height (68 and 214 mm, respectively) compared to TMI (88 and 303 mm, p<0.001, Figure 2a, 2c, 2d). Overall difference in GSH/GSSG between treatment groups was not significant but was markedly lower in aging mice (Figure 2b). No significant lung functional changes were apparent between treatment groups, although compliance and elastance were differed between adult versus aging mice. In the serum and lungs of mice treated with TBI, levels of MCP-1/JE were elevated (Figure 3a and 3d), although lung MCP-1 was not as elevated after TMI. Lung MMP2 was elevated after both TMI and TBI, and lung MMP9 was only elevated adult mice after TBI. Adult and aging mice treated with TBI also demonstrated increased levels of GRO/CXCL1/KC in the serum compared to TMI mice (Figure 3d), but only young adult mice showed a significant increase in MMP12 in the serum after TBI. Conclusions: TBI and TMI result in comparable early histologic changes within the marrow, although the effects of TMI on the GI tract were attenuated compared to TBI. Increased MCP-1 in the serum and lungs of TBI mice could lead to not only macrophage recruitment and activation but also T-cell chemotaxis into the lungs and other sites of antigen presentation, although this response was also attenuated in TMI. An early elevation in MMP12 (macrophage elastase) in adult mice could reflect a reactive mechanism against radiation damage that is less robust in aging mice. Figure 1. (a) TBI versus TMI with copper shielding, (b) percentage of KI67 positive cells in the bone marrow, (c) photomicrograph of Ki67 staining in the marrow, and (d) significant differences in marrow cytokines, growth factors, and MMPs between treatment groups. Figure 1. (a) TBI versus TMI with copper shielding, (b) percentage of KI67 positive cells in the bone marrow, (c) photomicrograph of Ki67 staining in the marrow, and (d) significant differences in marrow cytokines, growth factors, and MMPs between treatment groups. Figure 2. (a) Differences in villus height and crypt depth between treatment groups, (b) differences in oxidative stress as measured by GSH/GSSH ratio, (c) H&E stain of intestine from TBI recipient, and (d) H&D stain of intestine from TMI recipient. Figure 2. (a) Differences in villus height and crypt depth between treatment groups, (b) differences in oxidative stress as measured by GSH/GSSH ratio, (c) H&E stain of intestine from TBI recipient, and (d) H&D stain of intestine from TMI recipient. Figure 3. Differences in lung (a) MCP-1, (b) MMP9 (c) MMP2, and (d) serum cytokines and MMPs between treatment groups. Figure 3. Differences in lung (a) MCP-1, (b) MMP9 (c) MMP2, and (d) serum cytokines and MMPs between treatment groups. Disclosures No relevant conflicts of interest to declare.

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Asiamah, SD, C. Schandorf, and S. Anim-Sampong. "Performance of Harshaw 6600 thermo-luminescence dosimeter (TLD) system for personal monitoring." Journal of Applied Science and Technology 7, no. 1 (June 2, 2004). http://dx.doi.org/10.4314/jast.v7i1.17423.

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Gazy, Talaat. "Measurements of Entrance Skin Dose in Egyptian Pediatric During Diagnostic X-Rays using Thermo Luminescence Dosimeter (TLD -100)." Arab Journal of Nuclear Sciences and Applications, November 22, 2018, 0. http://dx.doi.org/10.21608/ajnsa.2018.2643.1056.

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Mehdizadeh, Mehrzad, Nasir Babakhan Kondori, Vahid Changizi, and Zahra Sadeghi. "Radiation Safety in Children in Children’s Medical Center Hospital." Iranian Journal of Pediatrics 30, no. 5 (September 14, 2020). http://dx.doi.org/10.5812/ijp.99887.

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Background: Diagnostic radiology studies in children harbor more radiation hazards than in adults due to their small size and higher cellular proliferation rate. Therefore, reducing the radiation burden to children should be top priority. Measurement of radiation dose is the first step to this goal. Nevertheless, we do not know whether the radiation of portable radiographs at our hospital meets the standards or not. Objectives: This study aims at measuring the primary and scattered radiation at different distances from patients. This eventually would help us to keep the radiation to minimum. Methods: This study was conducted on 84 patients from 4 different wards (U1-U2) in our hospital in 2017. After obtaining ethical approval from ethical committee and also written consent from parents, all patients who needed portable X-ray were included in our study. A thermo-luminescent dosimeter was placed on the patient’s chest to measure the entrance surface dose (ESD), while Geiger-Muller dosimeters located at one and two-meter distances from the X-ray tube used to scale the scattered radiation. Then, data were analyzed in SPSS 16. Results: The average ESD was 0.3873, 0.3867, 0.3700, and 0.4033 millisievert (mSv) in U1 to U4 respectively, whereas the scattered radiation doses measured as 0.00986, 0.00750, 0.01250, 0.1014 at one-meter and 0.00250, 0.00220, 0.00238, 0.00314 mSv at two-meter distances. There was no significant difference in radiation dose between those units (P > 0.05). Conclusions: Radiation received by patients in this study was three to four times higher than the standard dose. Significant scattered radiation was also detected at one and two-meter distances. To reduce radiation, improvement of exposure protocols such as reducing mAs and using proper shielding is emphasized.

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Mohamedy, Ebtesam M., Hassan Fathy, Wafaa M. Khalil, Nadia L. Helal, and Ehab M. Attalla. "Assessment the Photo-neutron Contamination of IMRT and 3D-Conformal Techniques Using Thermo-luminescent Dosimeter (TLD)." Journal of Pharmaceutical Research International, March 6, 2019, 1–10. http://dx.doi.org/10.9734/jpri/2018/v25i430107.

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The aim of the study is to evaluate the dependence of photo-neutron production on field size, depth in phantom and distance from isocenter and also to calculate the equivalent neutron doses for PTV and OARs of IMRT and 3DCRT techniques using TLD (600/700).The Linac Siemens Oncor installed at Nasser Institute, Cairo, Egypt. TLDs, Neutron Monitor, Ionization chamber were provided by NIS, the duration of the study was from November 2017 to July 2018. 5 prostate cancer cases were selected treated with high energy beam (15MV) Linear accelerator using 3DCRT and IMRT treatment plans. The OARs were bladder, rectum and femur. Once the plans were completed, there were copied from the planning system onto the RW3 slab phantom in which pairs of TLD chips (600/700) were placed at the exact site of PTV and OARs. The results showed that: The measured photo-neutron decreases from 0.2 mSv/Gy to 0.09 mSv/Gy as increases field sizes from 2x2 cm2 to 20x20 cm2. The measured photo-neutron was maximum at dmax =0.15 mSv/Gy and decreases gradually as increases the depth in phantom reaches to 0.07 mSv/Gy at 10cm depth in phantom. The measured photo-neutron decreases from 1.5 mSv/Gy to 0.02 mSv/Gy when measured at isocenter and at 100cm along the patient couch. Using 3DCRT for PTV and OARs were ranging from 0.027 to 0.39 mSv per photon Gy and for IMRT were 0.135 to 2.34 mSv per photon Gy. In conclusion the photo-neutron production is decreases as increases field size and distance from isocenter along patient couch while increases with depth in phantom up to dmax and decreases gradually as increases depth in phantom. IMRT requires longer beam-on time than 3DCRT leading to worse OARs sparing and increase the production of photo-neutrons than 3DCRT.

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Alalawi, Amani I., R. P. Hugtenburg, A. T. Abdul Rahman, M. A. Barry, A. Nisbet, Khalid S. Alzimami, and D. A. Bradley. "WITHDRAWN: Measurement of dose enhancement close to high atomic number media using optical fibre thermo luminescence dosimeters." Radiation Physics and Chemistry, February 2013. http://dx.doi.org/10.1016/j.radphyschem.2013.02.007.

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Paul, Sabyasachi, S. P. Tripathy, G. S. Sahoo, Meghnath Sen, S. C. Sharma, and M. S. Kulkarni. "Neutron spectrometry and dosimetry using a multi-shell Single Sphere Neutron Spectrometer with thermo-luminescent and optically stimulated luminescent detectors." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, May 2023, 168395. http://dx.doi.org/10.1016/j.nima.2023.168395.

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"A comparison of skin dose estimation between thermo-luminescent dosimeter and treatment planning system in prostatic cancer: a brachytherapy technique." Journal of Clinical and Translational Research, 2021. http://dx.doi.org/10.18053/jctres.07.202101.006.

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Majdaeen, Mehrsa, Masoumeh Dorri—Giv, Shaghayegh Olfat, Gholamreza Ataei, Razzagh Abedi-Firouzjah, Amin Banaei, and Sahar Ranjbar. "Skin dose measurement and estimating the dosimetric effect of applicator misplacement in gynecological brachytherapy: A patient and phantom study." Journal of X-Ray Science and Technology, June 23, 2021, 1–13. http://dx.doi.org/10.3233/xst-210911.

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OBJECTIVES: To evaluate skin dose differences between TPS (treatment planning system) calculations and TLD (thermo-luminescent dosimeters) measurements along with the dosimetric effect of applicator misplacement for patients diagnosed with gynecological (GYN) cancers undergoing brachytherapy. METHODS: The skin doses were measured using TLDs attached in different locations on patients’ skin in pelvic regions (anterior, left, and right) for 20 patients, as well as on a phantom. In addition, the applicator surface dose was calculated with TLDs attached to the applicator. The measured doses were compared with TPS calculations to find TPS accuracy. For the phantom, different applicator shifts were applied to find the effect of applicator misplacement on the surface dose. RESULTS: The mean absolute dose differences between the TPS and TLDs results for anterior, left, and right points were 3.14±1.03, 6.25±1.88, and 6.20±1.97 %, respectively. The mean difference on the applicator surface was obtained 1.92±0.46 %. Applicator misplacements of 0.5, 2, and 4 cm (average of three locations) resulted in 9, 36, and 61%, dose errors respectively. CONCLUSIONS: The surface/skin differences between the calculations and measurements are higher in the left and right regions, which relate to the higher uncertainty of TPS dose calculation in these regions. Furthermore, applicator misplacements can result in high skin dose variations, therefore it can be an appropriate quality assurance method for future research.

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Omidi, Reza, Fariba Farhadi Birgani, Ali Asghar Parach, Hamed Zamani, Saman Dalvand, Fatemeh Ezoddini-Ardakani, Nasim Namiranian, and Mohammad Hosein Zare. "Estimating the Entrance Surface Dose in the Eyes, Thyroid, and Parotid Gland Regions in Adult and Pediatric Groups: A Cone-Beam Computed Tomography Technique." Frontiers in Biomedical Technologies, December 26, 2021. http://dx.doi.org/10.18502/fbt.v9i1.8139.

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Purpose: This study aimed to determine the Entrance Surface Dose (ESD) of sensitive organs in Cone-Beam Computed Tomography (CBCT) imaging of the maxillofacial region in the two age groups of adult and pediatric. Materials and Methods: In this work, the measurements were performed using Thermo Luminescent Dosimeters (TLD-GR200). The imaging was performed using a PROMAX 3D CBCT scanner for 30 adults and 20 pediatric patients. The ESD value for each patient in the region of eyes, thyroid, and parotid glands was measured by 15 TLDs during CBCT of maxillofacial. Results: The highest and lowest mean values of ESDs were related to the parotid and thyroid gland regions in adults, 4.77 ± 0.61 mGy and 0.37 ± 0.16 mGy, respectively. In addition, these values were obtained 2.97 ± 0.36 mGy and 0.35 ± 0.12 mGy in pediatric groups as the highest and lowest values in that order. The results showed that the ESD values of the parotid gland regions in maxilla and mandible examinations had a significant difference (P <0.05). In addition, there was a significant difference between the ESD values of the parotid gland regions among the adults and pediatric groups (P <0.05). Conclusion: According to the results, the ESD values in both age groups were higher in the parotid gland region during maxillofacial CBCT examinations. Therefore, it is recommended to set radiation parameters like mAs as low as possible for reducing the patient dose, especially pediatric patients due to the more sensitive organs.

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Druzhinina, Yuliya, Sergey Ohrimenko, Zoya A. Lantukh, Ilya Soldatov, Sergey A. Ryzhkin, Viktor N. Lesnyak, Dmitry P. Lebedev, Denis Nikolaevich Samochatov, Marija Semenova, and Vitaliy Suhov. "Problems of personnel irradiation in modern medical technologies." Digital Diagnostics, June 15, 2023. http://dx.doi.org/10.17816/dd375327.

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BACKGROUND: The widespread use of radiation sources in medical practice (cardioendovascular surgery, endoscopy, traumatology, urology, neurosurgery, dentistry, radioisotope diagnostics departments) leads to irradiation of the lens of the eye and the skin of the hands with low-intensity scattered radiation. The introduction of new recommendations by the IAEA to reduce the limit of the annual equivalent dose to the lens (20 mSv), has led to incorrectness of the dose assessment for the lens, based on the effective dose. AIMS: Analysis of approaches and assessment of equivalent doses of irradiation of the lens of the eye and skin of the hands of medical personnel during various diagnostic studies under the influence of X-rays and gamma studies of radiopharmaceuticals, as well as comparison of the results obtained with previously published data. MATERIALS AND METHODS: The method of thermo-luminescent dosimetry was used. Dose assessment was carried out in the personnel of cardioendovascular surgery, endoscopy, isotope diagnostics, dentistry, and urology. RESULTS: The estimated annual equivalent doses to the lens of the eye for doctors of cardioendovascular surgery departments, in most cases, ranged from 35 to 90 mSv, the average medical staff - from 6 to 19 mSv (in some cases, the doctor - up to 225 mSv and the nurse - up to 180 mSv); the staff of the department of radioisotope diagnostics - from 4.5 to 9 mSv. The annual calculated equivalent doses to the skin of the hands were: cardioendovascular surgery personnel - from 17 to 100 mSv, and for the staff working with radiopharmaceuticals ‒ from 24 to 220 mSv. It is shown that the use of an estimate of the average dose per operation by cardioendovascular surgery doctors, as a rule, inevitably leads to an excess of the equivalent dose to the lens of the eye after a certain number of operations. CONCLUSION: Equivalent doses to the lens of the eye in cardioendovascular surgery doctors above 20 mSv per year can be formed when a certain number of operations is exceeded (from 100 to 200). A lesion of the lens of the eye in a cardio-endovascular surgery doctor was found at existing radiation levels. The results obtained indicate the need for further dosimetric measurements and epidemiological studies, on the basis of which recommendations can be developed for radiation protection of the lens of the eye and the skin of the hands of medical personnel working in the field of scattered, gamma, X-ray radiation of low intensity.

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