Relevant bibliographies by topics / TLD dosimeter

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Academic literature on the topic 'TLD dosimeter'

Author: Grafiati
Published: 4 June 2021
Last updated: 11 February 2022

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Journal articles on the topic "TLD dosimeter"

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

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The use of thermoluminescent dosimeters (TLDs) by personnel who work in radiation-rich environments is required by law. However, many professionals prefer to use Electronic Personal Dosimeters (EPDs), which provide dose estimation in real time. This preference may lead to a generalized use of the EPD instead of using the required TLD, as the use of both types at once can be uncomfortable and impractical. In an effort to avoid this scenario, a gamma/neutron dosimeter composed of a TLD and an EPD is being developed. In this paper, the results obtained from the studies performed in order to develop the neutron albedo dosimeter to be incorporated in the TLD[Formula: see text]EPD dosimeter are presented. Monte Carlo simulations using the state-of-the-art Monte Carlo N-Particle Transport (MCNPX) code were used to calculate the response of the albedo dosimeter. The thermal neutron detectors under consideration for use in the proposed dosimeter are the EJ-426 and the EJ-420. Both detectors employ a lithium compoundenriched to 95% [Formula: see text]Li dispersed in a ZnS:(Ag) matrix. The tomographic phantom Korean Typical Man-2 was used in the simulations to calculate the fraction of radiation backscattered by a human body in different radiation field conditions. From these results, it was concluded that both dosimeters are fit to be used as albedo dosimeters.
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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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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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Hernawan, Safarudin, Eka Djatnika Nugraha, Sutanto Sutanto, and Eri Hiswara. "PEMBUATAN THERMOLUMINESENSE DOSIMETER DARI BAHAN LITIUM FLUORIDA DAN PENGOTOR TITANIUM." Jurnal Forum Nuklir 10, no. 1 (June 7, 2017): 38. http://dx.doi.org/10.17146/jfn.2016.10.1.3492.

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PEMBUATAN THERMOLUMINESENSE DOSIMETER DARI BAHAN LITIUM FLUORIDA DAN PENGOTOR TITANIUM. Teknologi nuklir bermanfaat dalam berbagai bidang, misalnya bidang energi, pertanian, kedokteran, radiologi, lingkungan dan lain-lain, disamping itu paparan radiasi dari teknologi nuklir berdampak buruk bagi sel-sel tubuh manusia. perlu ada pengawasan terhadap pemanfaatan radiasi teknologi nuklir dengan menggunakan alat proteksi radiasi berupa dosimeter personal yaitu thermoluminesense dosimeter (TLD) yang saat ini pengunaannya di Indonesia masih di impor. TLD dapat dibuat dari bahan litium fluorida dengan variasi konsentrasi pengotor titanium 0,04%, 0,06%, dan 0,08% melalui metode kristalisasi dengan pemanasan pada suhu 950 celcius selama lima jam. kristal yang terbentuk dibuat serbuk dan diuji respon, keseragaman, kalibrasi, pemudaran dan pengulangan. hasil pembuatan menunjukkan TLD yang dibuat memiliki respon terhadap radiasi yang optimum pada konsentrasi pengotor titanium 0,06%. TLD yang dibuat memiliki faktor kalibrasi sebesar 0,0936 dan dapat diulang pemakaian sebanyak 5 kali. Pemudaran TLD yang dibuat sebesar 20% selama 14 hari.
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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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Nazaroh, Nazaroh. "KAJIAN ANALISIS KETIDAKPASTIAN TLD POSTAL IAEA/WHO SEBAGAI STANDAR PROGRAM AUDIT DOSIS." Jurnal Standardisasi 11, no. 2 (July 28, 2009): 73. http://dx.doi.org/10.31153/js.v11i2.634.

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<p>The International Atomic Energy Agency (IAEA) and World Health Organization (WHO) operate the IAEA/WHO TLD postal dose audit programme using thermoluminescence dosimeter (TLDs) for Secondary Standard<br />Dosimetry Laboratory (SSDL) and user every year. As National Reference Laboratory in the field of radiation metrology, PTKMR – BATAN always participates in the postal dose audit programme on therapy level for 60Co<br />beam. On the postal dose audit programme, the uncertainties in the dose determination from TLD measurements have been evaluated by IAEA, which is comprises of uncertainties in the calibration coefficient of the TLD system<br />and uncertainties in factors correcting for dose response non linearity, fading of TL signal, energy response, and influence of TLD holder. The individual uncertainties then have been combined to estimate the total uncertaintiy in<br />the dose evaluated from TLD measurements. The combined relative standard uncertainty in the dose determined from TLD measurements has been estimated to be 1.2% for irradiation with 60Co gamma rays and 1.6% for<br />irradiation with high-energy X-rays. Results from irradiations by Bureau Internationale des Poids et Mesures (BIPM), Primary Standard Dosimetry Laboratory (PSDL), and SSDL compare favourably with the estimated<br />uncertainties, whereas TLD results of radiotherapy centres show higher standard deviations than those derived theoretically. This paper presented the result of TLD postal dose audit for 60Co beam owned by PTKMR-BATAN<br />in the year of 2006-2008.</p>
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Rahman, M. Obaidur, Md Ashraful Hoque, Md Shakilur Rahman, and Afia Begum. "Responses of LiF Thermoluminescence Dosimeters to Diagnostic 60Co Teletherapy Beams." Bangladesh Journal of Medical Physics 8, no. 1 (September 10, 2017): 14–21. http://dx.doi.org/10.3329/bjmp.v8i1.33930.

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Thermoluminescence Dosimeter (TLD) is used as an ionizing radiation detector in the field of clinical radiotherapy, diagnostic radiology, personal radiation monitoring as well as in environmental radiation dosimetry. The sensitivity of all the TLDs is not the same even though the manufacturer produced them in the same batch. The response of TLD at various doses is also not always linear. In the present study fifty-seven rod shaped LiF TLDs had been irradiated by doses of 50cGy, 100cGy, 150cGy and 200cGy using 60Co teletherapy unit of Dhaka Medical College (Alcyon II, CGR, McV, France). The TLDs were placed in the grooves of a slab phantom and then covered by a 0.5cm thick plexiglass sheet. The phantom was then irradiated in the reference condition (10x10cm2 field size, 80cm SSD). After irradiation, readout of TLDs was done using a Harshaw TLD reader (Model 3500). Measurements were performed three times for each dose value and their average was taken. For convenience all fifty-seven TLDs were divided into nineteen groups. Grouping was done according to the response of the TLDs for a fixed dose value. In a particular group of TLDs, variation of the response of the dosimeters is the smallest one. The dose (cGy) – response (nC) linearity curve of TLDs for each of the nineteen groups showed to be very close to unity.Bangladesh Journal of Medical Physics Vol.8 No.1 2015 14-21
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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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Kartubi, Nazaroh, Assef Firnando Firmansyah, Pardi Pardi, and Caecilia Tuti Budiantari. "Preparation for Eye Lens Dose Assessment at CSTRM-NNEA." SciMedicine Journal 2, no. 1 (March 1, 2020): 30–37. http://dx.doi.org/10.28991/scimedj-2020-0201-5.

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Because of the negative impact of radiation on the eye lens and the changes recommended by the International Commission on Radiological Protection (ICRP) 103 (2007) from 150 to 20 mSv (2 rem, the Regulation of BAPETEN Head No. 4 (2013) article 56 give the instruction that Monitoring of eye lens dose should be implemented starting from March 13, 2016, more intensive around the eye lens. To prepare eye lens dose assessment, The Center for Safety Technology and Radiation Metrology (CSTRM) - NNEA study the response of TLD-700H against the X-ray: N (80), N (100) and N (120) energies (usually used in the interventional radiology). Goals and objectives of this study were to obtain the response/calibrated TLD-700H which is traceable to the international system (SI) and TLD-700H can be used for an eye lens dose assessment in Indonesia. Twenty-one TLDs were irradiated with seven dosage variations (0.1; 0.5; 1; 5; 10; 15; 20) mSv at the Secondary Standard Dosimetry Laboratory (SSDL) - Jakarta. After being stored for 24 hours, the TLD were read by using TLD-Reader. The Dosimeter Response, R against doses of X-ray were: R(N80) = 34.595x + 0.1262; R² = 0.9986; R(N100) = 24.484x + 1.1357; R² = 0.9993; and R(N120) = 27.908x - 5.1065; R² = 0.9971. R: correlation coefficient, x: doses; These calibration responses can be used for eye lens dose assessment in Indonesia.
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Grosser, Oliver Stephan, Heiko Wissel, Maurice Klopfleisch, Dennis Kupitz, Nadine Paetzold, Maciej Pech, and Michael C. Kreissl. "Time course and local distribution of skin exposure of hand and fingers from [68Ga]Ga-DOTA-NOC synthesis using a self-shielded module." Nuklearmedizin 59, no. 04 (March 25, 2020): 308–15. http://dx.doi.org/10.1055/a-1134-4374.

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Abstract Aim The study examined the local dose distribution as well as the time course of skin exposure of hand and fingers from [68Ga]Ga-DOTA-NOC synthesis using a self-shielded synthesis module. Methods A compact calibrated electronic dosimeter (ED) with a miniaturized probe was used for real-time measurements of skin dose equivalent Hp (0.07) (reference point: left and right index finger). A time resolved assessment of exposure during radiotracer production was performed. Additionally, thermoluminescence dosimeters (TLD) were used to determine local dose distribution for five different positions (e. g. fingertips). Cumulated Hp (0.07) estimated by ED was analysed and correlated with the measurements obtained by a TLD positioned close to the ED. Results The cumulative skin exposure from the production process measured by ED, was 74.7 ± 32.7 µSv/GBq and 40.1 ± 14.3 µSv/GBq for the right and left hand, respectively. The exposure recorded by the ED was in the average 19.4 % ± 40.0 % (median = 21.3 %) lower compared to the results from TLD. Highest exposure was recorded during synthesis (guided hand: 24.5 ± 12.2 µSv/GBq) and measuring of product yield including preparation of probes for quality control (guided hand: 36.1 ± 12.7 µSv/GBq). The highest local exposure was measured by a TLD close to the tip of the index finger of the guiding hand (range: 773–1257 µS/GBq). Conclusion The chosen methodology using ED, proved to be a good concept for identifying procedure steps with an increased exposure level and to determine the time course of skin exposure and to identify procedure steps for further optimization of handling. Furthermore, miniaturized electronic dosimeters may be used for online surveillance of local exposure rates at hands and fingers.
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Dissertations / Theses on the topic "TLD dosimeter"

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Hernandez, Pete Jevon. "Response comparison of an optically stimulated luminescent dosimeter, a direct-ion storage dosimeter, and a thermoluminescence dosimeter." [College Station, Tex. : Texas A&M University, 2008. http://hdl.handle.net/1969.1/ETD-TAMU-2979.

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Mendoza, Raul Ernesto Camargo. "Determinação de grandezas dosimétricas de interesse em mamografia usando detectores termoluminescentes." Universidade de São Paulo, 2010. http://www.teses.usp.br/teses/disponiveis/59/59135/tde-17042010-115247/.

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Os órgãos de saúde internacionais e nacionais, como o Ministério da Saúde na portaria 453/98 da Vigilância Sanitária, exigem que a Dose de Entrada na Pele seja avaliada para cada equipamento mamográfico através da leitura de um sistema câmara de ionização-eletrómetro corrigida pelo fator de retroespalhamento. Ao não existir menção explícita na portaría de valores utilizáveis para o fator de retroespalhamento, este trabalho visa à determinação experimental do fator de retroespalhamento, através da utilização dos dosímetros termoluminescentes TLD-100. No estudo são verificadas as dependências geométricas e espectrais do fator de retroespalhamento, assim como do valor da Dose de Entrada na Pele, e da Dose em Profundidade, correspondentes com as técnicas radiográficas empregadas nos exames mamográficos convencionais de rotina. Foram avaliados feixes na faixa de 0,35 mmAl até 0,43 mmAl, tensões do tubo de 25kV, 28kV, 30kV, e 32kV, assim como os três tamanhos de campo disponíveis no Mamógrafo Senographe DMR utilizado, e distancias focofilme iguais a 56cm, 61cm e 66cm. Os resultados obtidos foram comparados com publicações existentes, as quais apresentam resultados obtidos através de Simulação Monte Carlo, câmaras de ionização, e dosímetros TLD-100. Os resultados obtidos neste trabalho permitem estabelecer e discutir as dependências das grandezas dosimétricas estudadas com a Camada Semi-Redutora, tensão do tubo, combinação ânodo-filtro, tamanho de campo, distância foco-filme e espessura da mama.
National and international health organizations such as the Brazilian Ministry of Health, through its Secretary of Health Surveillance establishes in the publication Nº 453/98 that in all mammographic equipments must be evaluated the entrance-skin dose through the readings of an ionization chamber-electrometer system corrected by the backscatter factor, among others factors. Nevertheless, there is no explicit mention for useful values of backscatter factor in this document; the main aim of this work is the experimental determination of backscatter factor through the use of TLD-100 dosimeters. In this study, the geometric and spectral dependencies of the backscatter factor, entrance-skin dose and the in-depth dose were evaluated, corresponding to the most radiographic techniques employed in conventional mammographic procedures, i.e., beam qualities in the range of 0.35 mmAl to 0.43 mmAl, tube voltages from 25kV to 32kV, focus-film distances from 56cm to 66cm, and three field sizes were evaluated. Our results were compared with those previously published obtained through Monte Carlo simulation, ionization chambers and TLD dosimeters. The results obtained in this work allow studying the dependency of the mentioned dosimetric quantities with the half-value layer, tube voltage, anode-filter combination, field size, focusfilm distance and breasting thickness of the breast.
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Prause, Christopher Alvin. "External detection and measurement of inhaled radionuclides using thermoluminescent dosimeters." Texas A&M University, 2006. http://hdl.handle.net/1969.1/5021.

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Many radiation detection programs use bio-assays, whole-body counters, or air sampling to estimate internal doses. This study examines the possibility of using a common external thermoluminescent dosimeter (TLD) badge as a device for detecting inhaled radionuclides through radiation those radionuclides emit which escape the body. The three common radionuclides chosen for modeling due to their varying decay modes and use or production in the nuclear industry were Cs-137, U-238, and Sr-90. These three radionuclides were modeled for biological and radiological removal in the dynamic systems modeling program of STELLA II and modeled for TLD dose per organ in the geometry and radiation simulation program of MCNP. The results show that none of the nuclides in the study can be detected at air concentrations below regulatory limits for acute inhalation exposures. To achieve a detectable dose from an 8-hour work exposure, with a 90-day wait until the TLD is read, the airborne concentrations for the inhalation classes that produced the most dose per Bq would be 37.9 kBq/m3, 146 MBq/m3, and 1.67 MBq/m3 for Cs-137, U-238, and Sr-90, respectively.
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Baptista, Cláudia Gonçalves. "Correção de heterogeneidades para feixes de fótons de 6 MeV: comparações entre algoritmos de cálculo e medidas com TLD." Universidade Tecnológica Federal do Paraná, 2009. http://repositorio.utfpr.edu.br/jspui/handle/1/1047.

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O presente trabalho mostra as diferenças de dose encontradas em meios de diferentes densidades eletrônicas, simulando tecido adiposo, muscular, ósseo e cavidade aérea, comparando medidas experimentais com feixe de fótons de 6 MeV e valores resultantes de algoritmos de cálculo existentes em um sistema de planejamento radioterápico. Para isso foram utilizados dosímetros termoluminescentes posicionados acima, dentro e abaixo de cada objeto simulador e medidos os perfis de dose ao longo do eixo longitudinal e do eixo transversal. As simulações computacionais foram realizadas com dois algoritmos de cálculo presentes na versão 8.5 do sistema de planejamento Eclipse: o Pencil Beam Convolution e o Analytical Anisotropic Algorithm. Comparando doses em um mesmo ponto, com e sem heterogeneidades, foram encontradas diferenças percentuais de até 12%, quando os algoritmos de correção de heterogeneidades não foram aplicados. Analisando essas comparações, pode-se observar também qual dos algoritmos de cálculo mais se aproxima dos valores experimentais, propondo ser o algoritmo de maior confiabilidade.
This work presents the dose variations obtained when phantoms of different electronic densities were used, simulating fat tissue, muscle, bones and air cavities, comparing experimental data with a 6 MeV photon beams and the values calculated by the treatment planning system algorithms. Thermoluminescent dosimeters were positioned above, inside and below each phantom measuring the dose along the depth and along a profile. The computational simulation was done by two algorithms that are part of Eclipse version 8.5: Pencil Beam Convolution and Analytical Anisotropic Algorithm. Comparing doses at the same point, with and without heterogeneities, percentages of 12% were found when heterogeneity correction was not used. These results also show which of the algorithms approaches better to the experimental values, becoming more reliable.
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Paiva, Fabio de. "Estudo das respostas de TLD tipo LiF para caracterização de campos mistos." Universidade de São Paulo, 2016. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-18102016-105401/.

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A Terapia por Captura de Nêutrons, NCT (Neutron Capture Therapy) é uma técnica radioterápica em que a energia útil do tratamento vem da energia liberada em uma reação nuclear e não do feixe primário, como comumente utilizado em outros procedimentos radioterápicos. O Boro, por constituir-se em um elemento de baixa toxicidade e por apresentar um isótopo (10B) com alta seção de choque para a reação 10B(n,α)7Li tem sido o elemento mais utilizado nas pesquisas que visam o aprimoramento e a promoção desta técnica, derivando daí o termo BNCT (Boron Neutron Capture Therapy). Para fins de pesquisa em BNCT foi construída ao longo de um dos extratores de feixes (BH - Beam Hole) do reator IEA-R1 uma instalação, onde filtros e moderadores são posicionados entre o núcleo do reator e a posição de irradiação com o objetivo de modular o feixe de irradiação, otimizando a componente útil do feixe, os nêutrons térmicos, e reduzindo os contaminantes, raios gama e nêutrons em outras faixas energéticas. Tem-se realizado estudos visando a implementação de melhorias na caracterização e otimização do feixe obtido nesse arranjo instalado no BH-3. Atualmente a monitoração dos nêutrons é feita através de folhas de ativação, e a componente gama pelo TLD-400. Uma nova metodologia de monitoração tem sido estudada pelo grupo. A referida técnica consiste em usar TLDs de tipos diferentes, ou seja, que possuam sensibilidades distintas aos nêutrons térmicos, em virtude de diferenças na concentração dos isótopos de Lítio. No estudo dessa nova metodologia têm sido usados os TLD-600 e TLD-700. Este trabalho propõe uma metodologia usando o par TLD-100 e TLD-700. Inicialmente foi verificada a reprodutibilidade das respostas dos TLDs 700, 400 e 100 frente a campos gama puro e campos mistos, gama e nêutron. Campos estes obtidos em arranjos usando fontes de 60Co e 241AmBe. A partir de simulações usando o VI MCNP5 foi projetado e construído um Irradiador de campos mistos, que permitiu expor os dosímetros em campos mistos com diferentes espectros energéticos. As condições criadas no irradiador permitiram verificar, como a resposta do TLD é modificada pelas mudanças no espectro energético de um campo misto gama e nêutrons de baixo fluxo. O irradiador de campo misto permitiu condições para estabelecer uma relação entre o formato da curva termoluminescente e a composição do campo misto. A relação estabelecida relaciona o fluxo relativo e a razão entre a resposta das duas regiões de interesse dos TLDs 700 e 100. A partir de campos mistos com condições controladas, esse trabalho permitiu verificar a viabilidade do uso do par de TLD-100 e TLD-700 para monitoração de nêutrons térmicos na instalação de BNCT.
Neutron Capture Therapy (NCT), is a radiotherapy technique in which the useful treatment energy comes from the energy released in a nuclear reaction and not from the primary beam, as commonly used in other radiotherapc procedures. Boron, an element of low toxicity presents an isotope (10B) with high cross-section for the (n, α) reaction and therefore has been the element mostly used in research aimed at the improvement and promotion of this technique, deriving hence the term BNCT (Boron Neutron Capture Therapy). For BNCT research purposes, a facility was built along one of radiation extractors of the IEA-R1 reactor. In this facility filters and moderators are positioned between the reactor core and the irradiation position aiming to modulate the irradiation beam by optimizing the useful component of the beam, thermal neutrons, and reducing its contaminants, gamma rays and neutrons in higher energy bands. We have conducted studies aimed at implementing improvements in the characterization of and optimization of the beam. Currently, neutron flux monitorion is done through activation foils, and the gamma component by TLD-400. A new methodology has been studied by the group. The technique consists in using different types of TLD, having different sensitivities to thermal neutrons due to differences in the concentration of lithium isotopes. In the study of this new methodology TLD 600 and TLD-700 have been used. This work presents a series of studies in order to apply a methodology using the TLD-100 and TLD-700 pair. TLDs 700, 400 and 100 responses pure gamma and mixed irradiation fields, obtained in arrangements using a 60Co and AmBe sources, were evaluaterd. MCNP simulations were run in order to both discriminating the radiation components and designing one mixed fields irradiator, which allowed exposing dosimeters in mixed fields with different energy spectra. The conditions created in the irradiator allowed to verify, as the TLD response is modified by changes in the energy spectrum of a mixed gamma neutron fields. VIII This irradiator provided irradiation conditions so to establish a relationship between the shape of the LiF glow curves and the composition of the mixed field. This work has shown the feasibility of using the TLD-100 and TLD-700 pair for gamma and thermal neutrons monitoration in the BNCT facility.
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6

Santos, Lindomar Soares dos. "Implementação de um sistema dosimétrico termoluminescente para utilização em dosimetria in vivo em teleterapia com feixes de fótons de energia alta." Universidade de São Paulo, 2007. http://www.teses.usp.br/teses/disponiveis/59/59135/tde-12052008-150030/.

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A dosimetria in vivo é a verificação final da dose real administrada ao paciente e tornou-se atualmente necessária devido ao aumento da complexidade e da sofisticaçã das técnicas radioterápicas. A finalidade deste trabalho foi apresentar, verificar e avaliar alguns procedimentos básicos, práticos e viáveis para a implementação da dosimetria in vivo com dosímetros termoluminescentes na verificação de dose em um serviço de radioterapia. Para o estabelecimento do sistema dosimétrico termoluminescente, alguns testes e medições foram realizados, incluindo o procedimento de inicialização, a determinação da homogeneidade do grupo de dosímetros, a determinação do fator de correção individual de cada dosímetro, a determinação da faixa de linearidade do sistema e do coeficiente de calibração. Medições em um objeto simulador antropomórfico foram realizadas para garantir que os métodos utilizados são satisfatórios antes que estes fossem usados para medições em pacientes. Medições de dose em um paciente foram feitas em um tratamento de câncer de próstata. A metodologia proposta pode ser usada como parte de um programa de garantia de qualidade em um serviço de radioterapia.
In vivo dosimetry is the ultimate check of the actual dose delivered to an individual patient and has become a procedure actually necessary due to increasing complexity and sophistication of radiotherapy techniques. The purpose of the present work was to present, verify and evaluate some basic, practical and viable procedures for the implementation of in vivo dosimetry with thermoluminescent dosimeters for patient dose verification at a radiotherapy service. For the setting up of the thermoluminescent dosimetric system, several tests and measurements were carried out including the initialisation procedure, the determination of the batch homogeneity, the determination of individual correction factor of each dosimeter, the determination of linearity range of the system and its calibration coefficients. Anthropomorphic phantom measurements were taken to ensure that the methods are satisfactory before they are used for patients measurements. Patient dose measurements were carried out in a prostate cancer treatment. The proposed methodology can be used as a part of a quality assurance program in a radiotherapy service.
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7

Cavalieri, Tássio Antonio. "Emprego do MCNP no estudo dos TLDs 600 e 700 visando a implementação da caracterização do feixe de irradiação na instalação de BNCT do IEA-R1." Universidade de São Paulo, 2013. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-19112013-135350/.

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A Terapia de Captura de Nêutron por Boro (BNCT) é uma terapia de combate ao câncer bimodal, na qual a energia útil da terapia vem da reação nuclear que ocorre pelo Boro quando irradiado com nêutrons térmicos. No IPEN há uma instalação de pesquisas em BNCT, na qual o feixe de radiação contendo nêutrons é proveniente do reator IEA-R1. Como condição desta terapia é necessário realizar a dosimetria do feixe de radiação, que atualmente é feito com o uso de folhas de ativação, para cálculo do fluxo de nêutrons, e do dosímetro TLD 400, para estimativa da dose gama. Para campos mistos de nêutrons e gamas, a Comissão Internacional de Unidades e Medidas (ICRU) recomenda o uso de dosímetros com sensibilidades distintas para as componentes do feixe, como o caso do par TLD 600 e TLD 700 que apresentam sensibilidades distintas a nêutrons térmicos, devido à diferente quantidade do isótopo 6Li em sua composição, o qual apresenta uma alta seção de choque para nêutrons térmicos. Este trabalho constou da realização de simulações e experimentos visando a implementação da metodologia de dosimetria utilizando o par TLD 600 e TLD 700 e sua comparação com a metodologia atualmente utilizada pelo grupo de pesquisa em BNCT, que utiliza o TLD 400. Portanto, foi realizado um estudo das respostas de cada um destes TLDs a partir de irradiações em diferentes campos e sempre utilizando simulações com o MCNP para fornecer a discriminalização das componentes de dose depositadas em cada TLD. Foram realizadas varias irradiações em campo de gama puro e em campo misto de nêutrons e gamas para o estudo da reprodutibilidade destes TLDs. Este estudo mostrou que mesmo TLDs do mesmo tipo têm sensibilidades distintas, e assim foi criado um Fator de Normalização para cada um dos TLDs, eliminando assim a necessidade de selecionamento. Foi realizado um estudo sobre a diferença das respostas destes TLDs devido à diferentes campos. Este estudo mostrou ser possível estimar o fluxo relativo entre gamas e nêutrons a partir da relação existente entre as duas regiões de interesse dos TLDs 600 e 700. Também foi possível observar que o TLD 700 apresenta resposta para nêutrons, e se a recomendação da ICRU for seguida, a resposta devido à radiação gama será superestimada. Foram obtidas as curvas de calibração dose resposta destes TLDs para campos de gamas puro e campos mistos. Este trabalho propõe o uso desta metodologia com o uso do par TLD 600 e TLD 700, por apresentar maior precisão de resposta frente a atual metodologia que utiliza o TLD 400, porém precauções devem ser tomadas para evitar que a dose gama seja superestimada.
Boron Neutron Capture Therapy, BNCT, is a bimodal radiotherapic procedure for cancer treatment. Its usefull energy comes from a nuclear reaction driven by impinging thermal neutron upon Boron 10 atoms. A BNCT research facility has been constructed in IPEN at the IEA-R1 reactor, to develop studies in this area. One of its prime experimental parameter is the beam dosimetry which is nowadays made by using activation foils, for neutron measurements, and TLD 400, for gamma dosimetry. For mixed field dosimetry, the International Commmission on Radiation Units and Measuments, ICRU, recommends the use of pair of detectors with distinct responses to the field components. The TLD 600/ TLD 700 pair meets this criteria, as the amount of 6Li, a nuclide with high thermal neutron cross section, greatily differs in their composition. This work presents a series of experiments and simulations performed in order to implement the mixed field dosimetry based on the use of TLD 600/TLD 700 pair. It also intended to compare this mixed field dosimetric methodology to the one so far used by the BNCT research group of IPEN. The response of all TLDs were studied under irradiations in different irradiation fields and simulations, underwent by MCNP, were run in order to evaluate the dose contribution from each field component. Series of repeated irradiations under pure gamma field and mixed field neutron/gamma field showed differences in the TLD individual responses which led to the adoption of a Normalization Factor. From the use of Normalization Factor the TLD selection it has allowed to overcome TLD selection. TLD responses due to different field components and spectra were studied. It has shown to be possible to evaluate the ralative gamma/neutron fluxes from the relative responses observed in the two Regions of Interest of TLDs glow curves, ROIs, from TLD 600 and TLD 700. It has also been possible to observe the TLD 700 response to neutron, which leads to a gamma dose overstimation when one follows the ICRU recommended mixed field dosimetric procedure. Dose response curves were obtained for the distinct types of TLDs for pure gamma and mixed fields. This work recommends the TLD 600/TLD 700 pair methodology for mixed field dosimetry, this methodology presents a better precision than the one based on TLD 400, however one has to be carefull to avoid gamma dose superestimation.
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Mirzadeh, Kousha. "TLD Measurements on Patients being treated with a Taylor Spatial Frame : Using Radiation from Na18F PET/CT Studies and from Naturally Occurring Radioisotopes." Thesis, Stockholms universitet, Fysikum, 2014. http://urn.kb.se/resolve?urn=urn:nbn:se:su:diva-109361.

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Background: In an ongoing study conducted at Karolinska Institutet & Karolinska University Hospital, Positron Emission Tomography (PET)/Computed Tomography (CT) scans are performed on patients with tibia fractures and deformations treated with Taylor Spatial Frames (TSFs) in order to monitor their bone remodeling progress. Each patients receive an administration of approximately 2 MBq/kg bodyweight of Na18F associated with PET scans on two sessions, six and twelve weeks after the attachment of the TSF. These PET/CT scans provide information about the progress of the healing bone and can be used to estimate the optimal time point for de-attachment of the TSF. The Standardized Uptake Value (SUV) is used as a measure of the rate of bone remodeling for these patients, however, there is a need for verification of this practice by a method independent of the PET scanner. Furthermore, information regarding the biodistribution of the Na18F throughout the body of these patients and the effects of the TSF on the CT scan X‑rays is required. Additionally, an investigation of alternative methods that have the potential to provide similar information with a lower absorbed dose to the patients is desirable. Materials and methods: Thermoluminescent Dosimeters (TLDs) were attached on the skin at the position of the heart, urinary bladder, femurs, fracture, and the contralateral tibia of twelve patients during the first one hour and five minutes after the administration of the Na18F. Additional TLD measurements were performed during the CT scan of two of these patients. From the PET scan images, SUVs at the fracture site of these patients were collected. An investigation of the possibility of exploiting the “naturally” occurring bone seeking radionuclide Strontium-90 (90Sr) in the human body to gain information about the fracture site was undertaken. Using a 90Sr source, three different detection techniques were evaluated and a practical methodology for in vivo measurements on the tibia fracture patients was developed. As it was concluded that TLD based measurements were the most suitable technique for this purpose, and it was tested on five patients with tibia fractures. Results: From the collected TLD data, it was concluded that for these patients the urinary bladder is the organ receiving the greatest amount of absorbed dose and the organ most affected as the administered activity exceeds 2 MBq/kg. On average, a three times higher surface dose was measured on the tibia fracture compared to the un-fractured tibia. A linear relationship between the surface dose and SUVmax was shown. A strong positive correlation between the activity concentration at the fracture site and the amount of injected activity was found, and it was demonstrated that this also affects the SUVs. For patients who were administered different amounts of Na18F for the two PET scans, maximum activity concentrationwas less affected than mean activity concentration. It was concluded that TSF’s effect on the scatter of the X-rays to organs higher up in the body is negligible. Regarding “naturally” occurring 90Sr in the human body, no higher activity at the fractured tibia compared to the non‑fractured tibia could be found. Conclusions: This project assessed the accumulation of Na18F in the fracture site of patients treated with TSF by a method independent of the PET scanner. The methodology of using SUVs as an indicator for bone remodeling was verified. It was shown that the uptake of Na18F by the fracture site is strongly correlated to the amount of injected activity. The importance of considering the amount of injected activity when evaluating and comparing SUVs was highlighted. In vivo measurements using LiF:Mn TLDs did not indicate any quantifiable higher concentration of 90Sr at the fracture in the tibia bone.
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Broadhead, Dawn. "Large scale entrance surface dose survey and organ dose measurements during diagnostic radiology using the Harshaw 5500 and 6600 TLD systems." Thesis, University of Newcastle Upon Tyne, 2001. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.366517.

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Makhlouf, Oualid. "Nouveau modèle TLM thermique pour la dosimétrie numérique de structures fortement hétérogènes." Thesis, Université Côte d'Azur (ComUE), 2016. http://www.theses.fr/2016AZUR4123/document.

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Depuis plusieurs années, le développement des technologies sans fil utilisant les ondes électromagnétiques dans différents milieux d’applications (télécommunications, médicales, militaires) ne cesse d’augmenter. Il devient donc nécessaire d’évaluer les effets de l’environnement sur les antennes en amont de leur conception afin d’optimiser la transmission entre les divers objets connectés. De plus, les études sur les systèmes utilisant les ondes électromagnétiques amènent à se poser un certain nombre de questions autour de l’interaction ondes/vivant, nous obligeant à considérer des modèles fortement hétérogènes tel que le corps humain.Face aux difficultés de mesures, la simulation permet de quantifier numériquement la puissance absorbée par les tissus au travers du DAS et l’élévation de la température correspondante. Dans ce domaine, la méthode TLM (Transmission Line Matrix) s’est révélée être particulièrement adaptée au calcul du DAS dans des structures fortement hétérogènes grâce à la colocalisation des champs au centre de la maille.Au cours de cette thèse, un outil basé sur la méthode TLM permettant d’effectuer des études dosimétriques en calculant le DAS et la température dans des milieux fortement hétérogènes a été développé. La première étape a été consacrée au développement d’un « module »pour calculer la DAS et la mise en place d’une interface pour lire les modèles voxélisés. Ensuite, un solveur thermique basé sur la TLM a été développé afin de simuler la température dans des milieux biologiques exposés aux ondes EM. Enfin, la comparaison avec le logiciel commercial CST a permis de valider notre outil et de l’appliquer par la suite pour étudier l’exposition d’une tête humaine au rayonnement d’un Smartphone modélisé par une PIFA fonctionnant à 900MHz
For several years, the development of the wireless technologies using the electromagnetic waves in various applications (telecommunications, medical, military …) does not stop increasing. Thus, it becomes necessary to evaluate the effects of the environment on antennas upstream to their conception to optimize the transmission between diverse connected objects. Furthermore, studies on the systems using the electromagnetic waves lead to ask a number of questions about waves/living interaction, obliging us to consider highly heterogeneous models such as human body.In front of difficulties of measures, the simulation allows to quantify numerically the power absorbed by tissues and the corresponding temperature rise. In this domain, the TLM method (Transmission Line Matrix) has proved to be particularly adapted to the simulation of the SAR in highly heterogeneous structures thanks to the co-localisation of the fields at the centre of mesh.In this thesis, a tool based on the TLM method to make dosimetrics studies by calculating the SAR and the temperature in highly heterogeneous media has been developed. The first step was dedicated to the development of a “module” to calculate the SAR and the implementation of an interface to read the voxelized models. Then, a thermal solver based on the TLM was developed in order to simulate the temperature in biological media exposed to the EM waves. Finally, the comparison with the commercial software CST allowed to validate our tool and to apply it afterward to study the exposure of a human head to the radiation of a Smartphone modelled by a PIFA antenna operating at 900MHz
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Books on the topic "TLD dosimeter"

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S, Pradhan A., and Bhabha Atomic Research Centre, eds. Hand book on the use of TLD badge based on CaSo00 Z 8400 Z00:Dy TEFLON TLD discs for individual monitoring. Mumbai: Bhabha Atomic Research Centre, 2002.

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Martin, Colin J., and Dr David G. Sutton. Diagnostic radiology—patient dosimetry. Oxford University Press, 2015. http://dx.doi.org/10.1093/med/9780199655212.003.0014.

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A knowledge of the doses that patients receive is important to optimize radiation protection in diagnostic radiology. This chapter covers the methodology involved in assessment and management of patient dose for radiography and fluoroscopy. The dose quantities are described and ones to use for different applications are discussed. The instruments and measurement techniques used are described, including passive techniques such as TLD and radiochromic film. The need to consider scattering of X-rays from surfaces is explained. Factors to be taken into account include whether the assessment is for practical evaluation of technique or to provide an indication of risk. The appropriate dose to assess could be that to the whole body, the skin surface, or a particular organ such as the breast in mammography. These factors all feed into the patient dose audit process, which is explained together with the setting of diagnostic references levels to aid optimization.
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Measurement of residual radioactive surface contamination by 2-D laser heated TLD. Washington, DC: Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1997.

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Measurement of residual radioactive surface contamination by 2-D laser heated TLD. Washington, DC: Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1997.

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Book chapters on the topic "TLD dosimeter"

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Kinhikar, Rajesh A., Chandrshekhar M. Tambe, Dipak S. Dhote, and Deepak D. Deshpande. "In vivo dosimetry using MOSFET and TLD for Tomotherapy." In IFMBE Proceedings, 114–16. Berlin, Heidelberg: Springer Berlin Heidelberg, 2009. http://dx.doi.org/10.1007/978-3-642-03474-9_33.

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Daniel, Joshua D., Dale Henneke, and David W. Vehar. "The Effects of Radiation Hardening on the Reusability of CaF2:Mn TLDs." In Reactor Dosimetry: 16th International Symposium, 415–27. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2018. http://dx.doi.org/10.1520/stp160820170086.

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Rahimi, Seyed Ali. "Considering Dose Rate in Routine X-ray Examination by Thermoluminescent Dosimetry (TLD) in Radiology units of Mazandaran Hospitals." In IFMBE Proceedings, 582–85. Berlin, Heidelberg: Springer Berlin Heidelberg, 2008. http://dx.doi.org/10.1007/978-3-540-69367-3_155.

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Lores, Stefan Gutiérrez, and Gonzalo Walwyn Salas. "Implementation on Methodology for TLD Postal Dosimetry Audit of Radiotherapy Photon Beams in Non-reference Conditions in Cuba." In IFMBE Proceedings, 366. Berlin, Heidelberg: Springer Berlin Heidelberg, 2009. http://dx.doi.org/10.1007/978-3-642-03902-7_103.

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"Thermoluminescence dosimetry (TLD)." In Thermoluminescence of Solids, 205–52. Cambridge University Press, 1985. http://dx.doi.org/10.1017/cbo9780511564994.007.

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Conference papers on the topic "TLD dosimeter"

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Kartikasari, D., A. Zulys, E. Hiswara, and N. Nuraeni. "Synthesis of thermoluminescence dosimeter (TLD) using calcium sulfate (CaSO4) with variations of dysprosium (Dy) and thulium (Tm) dopants." In PROCEEDINGS OF THE 3RD INTERNATIONAL SYMPOSIUM ON CURRENT PROGRESS IN MATHEMATICS AND SCIENCES 2017 (ISCPMS2017). Author(s), 2018. http://dx.doi.org/10.1063/1.5064081.

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Deda, Antoneta, Ervis Telhaj, Beverly Karplus Hartline, Renee K. Horton, and Catherine M. Kaicher. "Determination of Radiation Energy Response for Thermoluminescent Dosimeter TLD-100: Determination of Organ Dose in Diagnostic Radiology (abstract)." In WOMEN IN PHYSICS: Third IUPAP International Conference on Women in Physics. AIP, 2009. http://dx.doi.org/10.1063/1.3137800.

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Mercado-Uribe, H. "TLD-100 and Radiochromic Dye Film in Medical Dosimetry." In ADVANCED SUMMER SCHOOL IN PHYSICS 2005: Frontiers in Contemporary Physics EAV05. AIP, 2006. http://dx.doi.org/10.1063/1.2160997.

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Azorín Nieto, Juan. "Thermoluminescence Dosimetry (TLD) and its Application in Medical Physics." In MEDICAL PHYSICS: Eighth Mexican Symposium on Medical Physics. AIP, 2004. http://dx.doi.org/10.1063/1.1811814.

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Squair, Peterson, Isabela Morais, Priscila Santana, Paulo Márcio Oliveira, Luiza Souza, and Maria Nogueira. "HVL mammography and tomosynthesis measurements with TLD system and different solid-state dosimeters." In Fifteenth International Workshop on Breast Imaging, edited by Chantal Van Ongeval, Nicholas Marshall, and Hilde Bosmans. SPIE, 2020. http://dx.doi.org/10.1117/12.2563998.

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Peña-Jiménez, Salvador, José Manuel Lárraga-Gutiérrez, Olivia Amanda García-Garduño, and Isabel Gamboa-deBuen. "Characterization of TLD-100 micro-cubes for use in small field dosimetry." In XIII MEXICAN SYMPOSIUM ON MEDICAL PHYSICS. AIP Publishing LLC, 2014. http://dx.doi.org/10.1063/1.4901385.

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Sanchez, Aridio M., Victor Brisan, and Anthony Difonzo. "TID Irradiation Facility Utilizing Novel Alanine Dosimetry." In 2016 IEEE Nuclear & Space Radiation Effects Conference (NSREC 2016). IEEE, 2016. http://dx.doi.org/10.1109/nsrec.2016.7891747.

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Makhlouf, Oualid, Marylene Cueille, and Jean-Lou Dubard. "TLM numerical thermal dosimetry in realistic environnement." In 2016 IEEE Radio and Antenna Days of the Indian Ocean (RADIO). IEEE, 2016. http://dx.doi.org/10.1109/radio.2016.7772028.

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Oliver, L., C. Candela, J. D. Palma, M. C. Pujades, A. Soriano, J. Alabau, J. Martinez, et al. "Comparison of the response of BeOSL and TLD-100 passive personal dosimeters with four detectors." In 2016 Global Medical Engineering Physics Exchanges/Pan American Health Care Exchanges (GMEPE/PAHCE). IEEE, 2016. http://dx.doi.org/10.1109/gmepe-pahce.2016.7504636.

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Makhlouf, Oualid, Marylene Cueille, and Jean-Lou Dubard. "A new TLM algorithm to solve the Pennes's equation for dosimetry applications." In 2015 European Microwave Conference (EuMC 2015). IEEE, 2015. http://dx.doi.org/10.1109/eumc.2015.7345933.

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Reports on the topic "TLD dosimeter"

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Casson, W. H., and G. T. Mei. Design of an advanced TLD-based fixed nuclear accident dosimeter. Office of Scientific and Technical Information (OSTI), August 1993. http://dx.doi.org/10.2172/10178185.

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Struckmeyer, R., and N. NcNamara. NRC TLD (thermoluminescent dosimeter) Direct Radiation Monitoring Network: Progress report, October--December 1988. Office of Scientific and Technical Information (OSTI), April 1989. http://dx.doi.org/10.2172/6124565.

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Nugent, K. J., A. B. Ahmed, and P. G. Groer. Evaluation of thermoluminescent dosimeters (TLDs) of two different designs for beta particle and low energy photon dosimetry. Office of Scientific and Technical Information (OSTI), November 1992. http://dx.doi.org/10.2172/6567527.

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Brackenbush, L. W., W. V. Baumgartner, and J. J. Fix. Response of TLD-albedo and nuclear track dosimeters exposed to plutonium sources. Office of Scientific and Technical Information (OSTI), December 1991. http://dx.doi.org/10.2172/5926091.

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Brackenbush, L. W., W. V. Baumgartner, and J. J. Fix. Response of TLD-albedo and nuclear track dosimeters exposed to plutonium sources. Office of Scientific and Technical Information (OSTI), December 1991. http://dx.doi.org/10.2172/10114950.

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6

Khalaf, M., and R. Thacker. HP-FO-TBD-508, Rev 0.2, Dosimeter Area Monitoring Program (DAMP) Technical Basis Document. Office of Scientific and Technical Information (OSTI), April 2021. http://dx.doi.org/10.2172/1778653.

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EVANS, C. L. Technical basis for setting Hanford Fire Department electronic dosimetry for emergency response (TBD-HSO-RC-009). Office of Scientific and Technical Information (OSTI), April 2003. http://dx.doi.org/10.2172/811855.

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Romero, L. L., J. M. Hoffman, E. M. Foltyn, and T. E. Buhl. Operational comparison of bubble (super heated drop) dosimetry with routine albedo TLD for a selected group of Pu-238 workers at Los Alamos National Laboratory. Office of Scientific and Technical Information (OSTI), September 1998. http://dx.doi.org/10.2172/304030.

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Liu, Chwei-jeng, C. Sims, and T. Rhea. Optimization of the readout procedures for the Harshaw 8800 TL (thermoluminescent) dosimetry system. Office of Scientific and Technical Information (OSTI), July 1989. http://dx.doi.org/10.2172/5873285.

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