Relevant bibliographies by topics / Dosimeters – Evaluation

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  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Dosimeters – Evaluation'

Author: Grafiati
Published: 4 June 2021
Last updated: 5 February 2022

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Journal articles on the topic "Dosimeters – Evaluation"

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Han, Moo Jae, Seung Woo Yang, Sang Il Bae, Young Min Moon, Wan Jeon, Chul Won Choi, Sung Kwang Park, and Jin Young Kim. "Evaluation of monoxide film-based dosimeters for surface dose detection in electron therapy." PLOS ONE 16, no. 5 (May 21, 2021): e0251441. http://dx.doi.org/10.1371/journal.pone.0251441.

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Generally, electron therapy is applied to tumors on or close to the skin surface. However, this causes a variety of skin-related side effects. To alleviate the risk of these side effects, clinical treatment uses skin dosimeters to verify the therapeutic dose. However, dosimeters suffer from poor accuracy, because their attachment sites are approximated with the help of naked eyes. Therefore, a dosimeter based on a flexible material that can adjust to the contours of the human body is required. In this study, the reproducibility, linearity, dose-rate dependence, and percentage depth ionization (PDI) of PbO and HgO film-based dosimeters are evaluated to explore their potential as large-scale flexible dosimeters. The results demonstrate that both dosimeters deliver impressive reproducibility (within 1.5%) and linearity (≥ 0.9990). The relative standard deviations of the dose-rate dependence of the PbO and HgO dosimeters were 0.94% and 1.16% at 6 MeV, respectively, and 1.08% and 1.25% at 9 MeV, respectively, with the PbO dosimeter outperforming the 1.1% of existing diodes. The PDI analysis of the PbO and HgO dosimeters returned values of 0.014 cm (–0.074 cm) and 0.051 cm (–0.016 cm), respectively at 6 MeV (9 MeV) compared to the thimble chamber and R50. Therefore, the maximum error of each dosimeter is within the allowable range of 0.1 cm. In short, the analysis reveals that the PbO dosimeter delivers a superior performance relative to its HgO counterpart and has strong potential for use as a surface dosimeter. Thus, flexible monoxide materials have the necessary qualities to be used for dosimeters that meet the requisite quality assurance standards and can satisfy a variety of radiation-related applications as flexible functional materials.
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Yoo, Wook Jae, Kyoung Won Jang, Jin Soo Moon, Ki Tek Han, Bong Soo Lee, Seung Hyun Cho, and Sin Kim. "Performance Evaluation of Scintillation Fiber-Optic Dosimeter for Measuring High-Energy Photon Beams." Advanced Materials Research 378-379 (October 2011): 701–5. http://dx.doi.org/10.4028/www.scientific.net/amr.378-379.701.

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In this study, we have fabricated a fiber-optic dosimeter using an organic scintillator and a plastic optical fiber for measuring percentage depth doses with radiotherapeutic high energy photon beams. The scintillating light generated in an organic dosimeter probe embedded in a solid water phantom is guided by a plastic optical fiber to the light-measuring device. Using this fiber-optic dosimeter, percentage depth doses are measured with 6 and 15 MV energies of photon beams whose field sizes are 2 x 2 and 10 x 10 cm2, and the results are compared with those measured using conventional dosimeters such as an ionization chamber and EBT films used in radiotherapy dosimetry.
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Apelmann, Kowald, Weinrich, Dischinger, Nienhaus, Seide, Martens, and Jürgens. "Radiation Dose to the Eye Lens Through Radiological Imaging Procedures at the Surgical Workplace During Trauma Surgery." International Journal of Environmental Research and Public Health 16, no. 20 (October 11, 2019): 3850. http://dx.doi.org/10.3390/ijerph16203850.

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Background: Due to the drastic reduction of the eye lens dose limit from 150 mSv per year to 20 mSv per year since 2018, the prospective investigation of the estimated dose of the eye lens by radiological imaging procedures at the surgical site during trauma surgery in the daily work process was carried out. This was also necessary because, as experience shows, with changes in surgical techniques, there are also changes in the use of radiological procedures, and thus an up-to-date inventory can provide valuable information for the assessment of occupationally induced radiation exposure of surgical personnel under the current conditions. Methods: The eye lens radiation exposure was measured over three months for five trauma surgeons, four hand surgeons and four surgical assistants with personalized LPS-TLD-TD 07 partial body dosimeters Hp (0.07). A reference dosimeter was deposited at the surgery changing room. The dosimeters were sent to the LPS (Landesanstalt für Personendosimetrie und Strahlenschutzausbildung) measuring institute (National Institute for Personal Dosimetry and Radiation Protection Training, Berlin) for evaluation after 3 months. The duration of the operation, occupation (assistant, surgeon, etc.), type of surgery (procedure, diagnosis), designation of the X-ray unit, total duration of radiation exposure per operation and dose area product per operation were recorded. Results: Both the evaluation of the dosimeters by the trauma surgeons and the evaluation of the dosimeters by the hand surgeons and the surgical assistants revealed no significant radiation exposure of the eye lens in comparison to the respective measured reference dosimeters. Conclusions: Despite the drastic reduction of the eye lens dose limit from 150 mSv per year to 20 mSv per year, the limit for orthopedic, trauma and hand surgery operations is well below the limit in this setting.
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Einbergs, E., A. Zolotarjovs, I. Bite, J. Cipa, V. Vitola, K. Laganovska, and L. Trinkler. "Re-Evaluation of Chromium Doped Alumina for Dosimetric Applications." Latvian Journal of Physics and Technical Sciences 58, no. 1 (January 29, 2021): 15–22. http://dx.doi.org/10.2478/lpts-2021-0002.

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Abstract Many medical examinations involve ionizing radiation. Although the range of available dosimeters is rather wide, their linearity and chemical stability are limited. Recently, there has been a growing interest in new, improved dosimetric materials for emerging applications in medicine and other fields, such as sterilisation of consumer goods and medical instruments, irradiation of seeds, chemical agents and others. One of the classical dosimeters is carbon-doped alumina (Al2O3:C) – a well-established and widely used material for personal and industrial dosimeter with a range of great properties, such as high sensitivity, wide linearity range and relative ease of production and handling. However, the demand for reliable dosimeters in a high-dose range is still only partially fulfilled, and alumina doped with chromium ions (Al2O3:Cr) can be a promising candidate. In this study, we explored alumina doped with chromium porous microparticles synthesized with a sol-gel method as a possible high dose dosimeter and evaluated its thermostimulated luminescence signal, dose response with two irradiation sources and measured long-time fading. It was found that although the TSL signal was quite complex (consisting of two main peaks above room temperature) and the long-term fading was significant (around 50 % in the span of 30 days), with sufficient optimisation the material could be used as a high-dose dosimeter for X-ray and beta irradiation. Wide high dose linearity range, physical and chemical characteristics, as well as low production costs and ease of synthesis make chromium (III) doped alumina a compelling candidate for applicability in various medical and industry fields.
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Rabaeh, Khalid, and Ahmed Basfar. "Optical evaluation of dithizone solution as a new radiochromic dosimeter." Pigment & Resin Technology 49, no. 4 (February 28, 2020): 249–53. http://dx.doi.org/10.1108/prt-10-2019-0091.

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Purpose The purpose of this paper is to propose a new dithizone solution dosimeter for high radiation applications such as polymers applications and food irradiation. Design/methodology/approach Gamma-rays cell of Co-60 source with 8.4 kGy/h dose rate was used to irradiate the dithizone solutions at different irradiation temperatures. The optical measurements of unirradiated and irradiated dithizone dye solution dosimeters were performed using a UV/VIS spectrophotometer at absorption peaks of 421 and 515 nm. Findings The new dosimeter improved significantly with the increase of dithizone dye concentrations from 0.025 to 0.1 mM. The dosimeter shows a perfect pre- and post-irradiation stability after irradiation for five days. Because of irradiation temperature dependence, the dithizone solution dosimeter should be corrected under actual processing conditions. Practical implications Dosimetry is a key point in quality control of radiation processing to assure that uniform and correct radiation doses are delivered to a region of interest. Therefore, this study introduces a dithizone solution dosimeter for high-dose radiation applications such as food irradiation, polymers applications and agriculture. Originality/value Ionizing radiation interacted with the ethanol solvent, resulting in the formation of free radicals, then these free radicals interacted with the dithizone molecule and changed the dye color from yellow to orange.
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Siti, K. A. R., S. M. Iskandar, A. R. Azhar, M. R. Ramzun, and Mohamed Kamari Halimah. "Acoustic Evaluation of Hema Polymer Gel Dosimeter Phantoms." Advanced Materials Research 895 (February 2014): 169–73. http://dx.doi.org/10.4028/www.scientific.net/amr.895.169.

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A new method for the evaluation of radiotherapy 3D polymer gel dosimeters has been developed using ultrasound to assess the significant structural changes that occur following irradiation of the dosimeters. Polymer gel dosimeters were being fabricated using a monomer named 2-Hydroxyl-Ethyl-Meta-Acrylate (HEMA) with the presence of gelatine as a gelling agent. The readymade gel which is the concentration for HEMA fixed at 2, 4 and 5% would then undergo an ultrasonic evaluation to test for the propagation of sound speed through it. In the observation of relationship between the ultrasound propagation speeds as the doses increase (focusing at the cross region from overlapped beams) and concentration of monomer, the propagation speed for all the three polymer gel dosimeter phantoms still varies between 1460 to 1570 m/s which is still in the range of speed of sound for human tissue [. The ultrasonic absorption attenuation coefficient dose sensitivity for polymer gel dosimeters for 2, 4 and 5% of monomer are in the range of 0.02 to 0.6 dB which is equivalent to human tissue. As a comparison, it can be seen that gel phantoms with high concentration of monomer (5%) is more sensitive to the radiation compared to the lower (2% and 4%) concentrations. Regarding the absolute results of mechanical and acoustic properties; the copolymer-in-oil phantom is equivalent with soft tissue.
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Gerasia, Roberta, Dario Ligresti, Fabio Cipolletta, Antonino Granata, Ilaria Tarantino, Luca Barresi, Michele Amata, et al. "Endoscopist’s occupational dose evaluation related to correct wearing of dosimeter during X-ray-guided procedures." Endoscopy International Open 07, no. 03 (February 28, 2019): E367—E371. http://dx.doi.org/10.1055/a-0841-3350.

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Abstract Background Since endoscopists performing procedures in the endoscopy suite can change their position by turning their back, side or front toward the X-ray source, this study aimed to establish whether dosimeter position affects the correct evaluation of an endoscopist’s personal radiation exposure during X-ray-guided procedures. Materials and methods Between January and February 2018, two dosimeters specularly placed outside the lead apron (anterior one on the chest and posterior one on the back) measured endoscopists’ personal dose equivalent (Hp) during 62 X-ray-guided procedures on adult and pediatric patients. Procedures were divided into three groups considering the position taken by the endoscopist with respect to the radiation source. For each group, the difference between mean Hp from the anterior and posterior dosimeters was calculated. Results A statistically significant difference in mean Hp was recorded for the endoscopists’ frontal and back positions (P = 0.014, and P < 0.00001, respectively). No significant difference was found in mean Hp for the side position (P = 0.489). Conclusions The position of personal dosimeters affects the correct evaluation of endoscopists’ radiation exposure during X-ray-guided procedures when frontal and back positions were recorded. To correctly evaluate radiation doses, the whole-body dosimeter should be worn according to the position of the endoscopist with respect to the radiation source; otherwise, it results in an incorrect personal dose evaluation, which may lead to substantial underestimation of staff exposure.
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Abraheem, Abeer Z., F. Khamis, and Y. A. Abdulla. "TL Characteristics and Dosimetric Aspects of Mg-Doped ZnO." European Journal of Applied Physics 3, no. 1 (January 29, 2021): 43–47. http://dx.doi.org/10.24018/ejphysics.2021.3.1.37.

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Dosimetry characterization and the evaluation of kinetics parameters of trapping states of Mg-doped ZnO phosphors synthesized by Sol-Gel technique. The thermoluminescence response of Mg-doped ZnO samples showed a linear response when exposed to X-ray radiation and the optimum annealing condition was 400oC/4h for the three concentrations. A broad-shaped TL glow curve with an upper bound of 270 °C, which shifts to lower temperatures with increasing dose, indicating that general order (GO) kinetics thermoluminescence processes are involved. We conclude that the ZnO doped Mg phosphors under study are promises to develop dosimeters for high radiation dose measurements. Kinetic parameters, such as activation energy (E), frequency factor (s), and order of kinematic order (b), were estimated by the Glow Curve Deconvolution (GCD) method. ZnO:Mg phosphor has a great potential as a dosimeter for monitoring in the fields of ionizing radiation.
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de Almeida, Shirlane Barbosa, Daniel Villani, Roberto Kenji Sakuraba, Ana Carolina Pires de Rezende, Silas Cardoso Santos, and Letícia Lucente Campos. "Dosimetric evaluation employing TL and OSL techniques with different luminescent materials for clinical evaluation of extremity doses using electron beams applied to Total-Irradiation-of-Skin treatments." International Journal of Modern Physics: Conference Series 48 (January 2018): 1860110. http://dx.doi.org/10.1142/s2010194518601102.

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Total-skin electron beam (TSEB) irradiation is used to deliver a homogeneous dose distribution over the entire skin surface of a patient. TSEB dosimetry is quite complex as to the evaluation and measurement of absorbed dosage in the cutaneous region. This paper evaluates the performance of different dosimetric materials, using TL and OSL dosimetry, in the extremity-dose assessment of TSEB treatments using the six-dual-field technique and an anthropomorphic phantom. Dosimeters were selected with repeatability better than [Formula: see text] and calibrated to 6-MeV electron-beam dosimetry. Measurements were conducted in the abdominal region as a reference point and on the extremities. Results show expected deviations ranging up to [Formula: see text] in the dose received in the extremities and good results in dose assessment using all dosimetric materials tested.
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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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Dissertations / Theses on the topic "Dosimeters – Evaluation"

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Griffis, Neale Jeff. "Performance evaluation of the Dosicard electronic personal dosimeter." Thesis, Georgia Institute of Technology, 2001. http://hdl.handle.net/1853/16991.

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Lhallabi, Abdessamad. "Evaluation des incertitudes dans la preparation et la realisation des traitements par radiotherapie transcutanee." Toulouse 3, 1987. http://www.theses.fr/1987TOU30076.

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Langdal, Ingrid. "Dosimetry and evaluation of algorithm for inverseoptimized doseplanning for brachytherapy." Thesis, Norwegian University of Science and Technology, Department of Physics, 2009. http://urn.kb.se/resolve?urn=urn:nbn:no:ntnu:diva-6287.

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Purpose

Individual optimized treatment planning is recommended when creating treatment plans for brachytherapy of cervical cancer. Manual alteration of the dose distribution is time consuming and the treatment plan may be dependent on the person creating it. Inverse planning simulated anneahng (IPSA) is an algorithm that can optimize the dose distribution considering dose to several delineated structures. This algorithm, currently available in the treatment planning system Masterplan, has been evaluated for brachytherapy of cervical cancer. The Masterplan system simulates a source type from at different manufacturer than the type used for treatment at St. Olavs Hospital at the time being. The dose distribution from the two source types were evaluated to see if Masterplan an be used to simulate the source type used for treatment at St. Olavs Hospital.

Methods and materials

The dose distributions from the two source types were compared based on calcuations from two treatment planning systems (Masterplan and Plato) simulating each source type.

Dose measurements of the source used at St. Olavs Hospital for brachytherapy treatment of cervical cancer were taken. These were compared with the dose distribution calculated by the two treatment planning systems.

At St. Olavs Hospital treatment are executed using a Fletcher type applicator. MR-images are taken with the applicator in place. Target and organs at risk are delineated in the images before the treatment planning is performed. For 11 patients treated with brachytherapy of cervical cancer at St. Olavs Hospital, three different IPSA-plans with different dose constraints (IPSA1, IPSA2 and IPSA3) and one treatment plan with equal dwell times were made in retrospect. All IPSA-plans constrain the same dose to the target. IPSA1 and IPSA3 have the same constraints to organs at risk, while IPSA2 allow a higher dose to the organs at risk. IPSA3 sets a limit for maximum dose in target volume. For evaluation of the quality of the treatment plans, dose parameters of chnical relevance were extracted from dose volume histograms.

Results

Deviations in the calculated dose distribution up to 30% is found for the two source types in certain areas. These deviations are found close to the source and below the connector end of the source. For distances ≥ 4 mm from the source center along one axis, deviations of the calculations were ≤ 4%. This is in correspondance with the measured dose values.

Target coverage for IPSA2 is 0.92. For IPSA1 and IPSA3 target coverage is 0.84 and 0.81 respectively. The number of treatment plans exceeding tolerance limit for one or more OAR is 82% for IPSA2, 55% for IPSA1 and 35% for IPSA3. The plan with equal dwell times have a target coverage of 0.66 and 45% of the treatment plans exceed the given tolerance limit for one or more organs at risk.

Conclusion

Deviations are found in the simulated dose distribution of the two source types tested, but only in clinical irrelevant areas for brachytherapy of cervical cancer. Masterplan can be used for simulating the dose distribution of the source used for treatment at St. Olavs Hospital.

Using IPSA is better when it comes to improving target coverage and not violating tolerance limit for organs at risk, than a conservative treatment plan with equal dwell times. Due to too high doses to organs at risk, IPSA2 should be rejected. IPSA1 has better target coverage and IPSA3 have lower dose to the organs at risk. To avoid inhomogeneities in dwell time values, IPSA3 is probably the best suggestion.

 


Sammendrag

Formål

Det er anbefalt & lage individuelt optimaliserte plan når behandlingsplaner skal lages i forbindelse med brachyterapi av livmorhalskreft. Manuell endring av dosefordelingen er tidkrevende og resultatet kan bli preget av personen som lager planen. 'Iverse planning simulated anneahng' (IPSA) er en algoritme som kan optimalisere dosefordehngen slik at dose til flere skisserte strukturer blir tatt hensyn til. Denne algoritmen, tilgjengehg i doseplanleggingssystemet Masterplan, har blitt vurdert for brachyterapi av livmorhalskreft.

Masterplan simulerer en kildetype fra en annen produsent enn den kildetypen som blir brukt til behandling på St. Olavs hospital i dag. Dosefordehngen til de to kildetypene har blitt vurdert for å se om Masterplan kan brukes til å simulere kildetypen brukt til behandling.

Metode og utstyr

Dosefordehngen fra de to kildetypene ble sammenlignet ved hjelp av doseberegninger fra to doseplanleggingssystemer (Masterplan og Plato) som simulerer hver sin kildetype.

Det ble tatt målinger av dosen fra kilden brukt på St. Olavs hospital til brachyterapi av livmorhalskreft. Disse ble sammenlignet med dosefordelingen regnet ut av de to planleggingssystemene.

På St. Olavs hospital blir en Fletcher type apphkator brukt til behandling. MR-bilder blir tatt etter at applikatoren er posisjonert. I bildene blir målvolum og risikooganer skissert før behandlingsplanleggingen gjennomføres. I denne studien har tre ulike IPSA-planer med forskjellig doserestriksjoner (IPSA1, IPSA2 and IPSA3) og en plan med lik liggetid i kildeposisjonene, blitt laget i ettertid for 11 pasienter behandlet for livmorhalskreft på St. Olavs hospital. IPSA-planene har samme doserestriksjoner til målvolum. IPSA1 og IPSA3 har samme begrensning til risikoorganer, mens IPSA2 tillater høyere dose til risikoorganer. IPSA3 har en begrensning for maksimum dose til volum for måvolumet. For vurdering av kvaliteten til planene ble klinisk relevante doseparametre funnet fra dosevolum-histogram.

Resultat

Det ble funnet avvik opp til 30% for beregnet dose i ulike punkt for de to kildetypene i visse omr&der. Disse avvikene ligger nærme kilden og rett under koblingsenden. For avstander ≥ 4 mm fra kildesenter transversalt på kilden er avvikene i beregningene ≤4%. Dosemålingene som ble tatt støtter dette.

Dekning av målvolum er 0.92 for IPSA2. For IPSA1 og IPSA3 er denne dekninjen henholdsvis 0.84 og 0.81. Antall planer hvor en definert grense for dosen til et eller flere risikoorgan har blitt oversteget, er 82% for IPSA2, 55% for IPSA1 og 35% for IPSA3. Planen hvor liggetidene er fordelt likt har malvolumdekning på 0.66 og 45% av planene overstiger den definerte toleranse grensen for et eller flere risikoorgan.

Konklusjon

Det ble funnet avvik i de simulerte dosefordelingene mellom de to kildetypene, men kun i klinisk irrelevante områder for brachyterapi av livmorhalskreft. Masterplan kan bli brukt til å simulere dosefordelingen til kilden som blir brukt til behandling på St. Olavs hospital.

Bruk av IPSA gir bedre resultater enn den konservative behandlingsplanen med lik liggetid ncir det gjelder dekning av målvolum og å overholde toleransegrensene som er satt for risikorganene. På grunn av for høye doser til risikoorganer burde IPSA2 forkastes. IPSA3 gir bedre dekning av måvolum mens IPSA3 gir lavere dose til risikoorganer. For å unngå store forskjeller mellom liggetidene i de ulike kildeposisjonene vil antagelig IPSA3 gi best utganspunkt for videre planlegging.

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PASCOALINO, KELLY C. da S. "Estudo comparativo das respostas de diodos de Si para dosimetria de radiacao gama." reponame:Repositório Institucional do IPEN, 2010. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9517.

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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Pollitt, David Frederic. "Performance evaluation of a second generation metaphase finder for chromosome-based radiation dosimetry." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 1998. http://www.collectionscanada.ca/obj/s4/f2/dsk2/tape17/PQDD_0009/MQ32550.pdf.

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Tölli, Heikki. "Ionization chamber dosimetry for brachytherapy evaluation of correction factors for absorbed dose determination /." Göteborg : Dept. of Radiation Physics, University of Göteborg, 1997. http://catalog.hathitrust.org/api/volumes/oclc/38990266.html.

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Meesat, Ridthee. "Evaluation of the radiosensitizing or radioprotective/antioxidant potential of some selected compounds by polyacrylamide gel dosimetry and Fricke dosimeter, and utilization of the femtosecond infrared laser pulse filamentation as a novel, powerful beam for cancer radiotherapy." Thèse, Université de Sherbrooke, 2012. http://hdl.handle.net/11143/6246.

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In radiation treatment, a sufficiently high radiation dose must be delivered to the tissue volumes containing the tumor cells while the lowest possible dose should be deposited in surrounding healthy tissue. We developed an original approach that is fast and easy to implement for the early assessment of the efficiency of radiation sensitizers and protectors. In addition, we characterized a new femtosecond laser pulse irradiation technique. We are able to deposit a considerable dose with a very high dose rate inside a well-controlled macroscopic volume without deposition of energy in front or behind the target volume. The radioprotective efficiency was measured by irradiation of the Fricke solution incorporating a compound under study and measuring the corresponding production of ferric ions G (Fe3+ ). The production of ferric ions is most sensitive to the radical species produced in the radiolysis of water. We studied experimentally and simulated with a full Monte-Carlo computer code the radiation-induced chemistry of Fricke/cystamine solutions. Results clearly indicate that the protective effect of cystamine originates from its radical-capturing ability, which allows this compound to compete with the ferrous ions for the various fre radicals - especially · OH radicals and H· atoms - formed during irradiation of the surrounding water. The sensitizing capacity of radiation sensitizers was measured by irradiation of a polyacrylamide gel (PAG) dosimeter incorporating a compound under study and measuring the corresponding increase in the gradient between spin-spin relaxation rate (R2 ) and absorbed dose. We measured an irradiation energy-dependent increase in R 2 -dose sensitivity for halogenated compounds or a decrease for radioprotectors. Finally, we studied a novel laser irradiation method called "filamentation". We showed that this phenomenon results in an unprecedented deposition of energy and the dose rate thus achieved exceeds by orders of magnitude values previously reported for the most intense clinical radiotherapy systems. Moreover, the length of the dose-fre entrance region was adjusted by selecting the duration of femtosecond laser pulses. In addition, we provided evidence that the biological damage caused by this irradiation was similar to other ionizing radiation sources. [symboles non conformes]
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MARRE, DELPHINE. "Evaluation des perturbations induites sur la mesure de la dose absorbee avec des chambres d'ionisation, des dosimetres chimiques et des dosimetres thermoluminescents dans des faisceaux d'electrons de haute energie." Toulouse 3, 2000. http://www.theses.fr/2000TOU30083.

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Le but de cette these est d'ameliorer la precision sur la determination de la dose absorbee avec des detecteurs usuels en radiotherapie, en particulier les chambres d'ionisation, les dosimetres chimiques et les dosimetres thermoluminescents (dtl), dans des faisceaux d'electrons de haute energie. En effet, la composition de ces detecteurs est generalement differente de celle du milieu environnant, ce qui engendre des perturbations sur la mesure de la dose absorbee. Le but recherche est de determiner les differents facteurs de correction qui sont associes a ces detecteurs dans les faisceaux d'electrons de 6 a 50 mev. Une approche experimentale et deux approches theoriques sont menees : la dosimetrie de fricke est prise comme reference pour la partie experimentale. Des calculs par la methode de monte carlo (egs4 et penelope) et la theorie generale de la cavite sont utilises pour la theorie. Les resultats theoriques sont ensuite confrontes aux mesures. La determination de la dose absorbee avec les chambres d'ionisation dans les faisceaux d'electrons s'effectue par l'application des protocoles de dosimetrie (par exemple iaea 1997 et 2000). Ces protocoles donnent des valeurs de facteurs de correction plus ou moins approchees pour certaines chambres d'ionisation, alors que d'autres ne sont pas repertoriees. Notre etude consiste a evaluer avec la meilleure precision possible les facteurs de correction de perturbation et de correction de qualite de faisceau pour les chambres d'ionisation plates et cylindriques. Notre etude des dtl consiste a evaluer le facteur de correction de qualite de faisceau pour le lif sous forme de poudre (dtl937). L'energie du faisceau d'electrons, les dimensions du dtl et la nature du milieu environnant sont les parametres d'influence etudies. Les resultats obtenus sont actuellement directement appliques pour la determination de la dose absorbee par dtl dans le laboratoire europeen de controle de qualite en radiotherapie equal-estro installe a l'igr.
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Belanger, Philippe. "MR based frickle-gelatin dosimetry : uncertainty evaluation and computerised analysis of measured dose distributions." Thesis, McGill University, 2001. http://digitool.Library.McGill.CA:80/R/?func=dbin-jump-full&object_id=32759.

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Dynamically delivered intensity modulated beams (IMBs) pose unique verification problems that may be addressed with the use of integrating continuous 3D dosimeters such as gel based Fricke dosimeters. Accurate knowledge of the ability of these dosimeters to measure adequately and precisely the delivered dose is a prerequisite for their clinical use. The magnetic properties of the ferrous and ferric ions present in the gel based Fricke dosimeter after its irradiation are the basis for the use of magnetic resonance imaging (MRI) in the measurement of dose. This thesis presents the investigation of a 3D gel based Fricke dosimetry system (Fricke-gel). A software system is developed and spin-lattice relaxation rate (R1) images are computed from MR images of irradiated Fricke-gel phantoms in order to quantify the dosimetric uncertainties resulting from the MR imaging system, from the gel itself, as well as from the external parameters. The sensitivity and the minimum detectable dose of the Fricke-gel dosimeter are determined. Validation of the dosimeter's capacity to measure dose distributions is made through measurement of percent depth dose curves (PDD's), and field profiles (open and wedged). An example of clinical utilisation of the Fricke-gel dosimeter is presented. Dose distributions are evaluated visually by 3D software tools and quantitatively analyzed by dose-volume histograms. Results show a good correlation between the Fricke-gel measured dose distributions and treatment planning software dose calculations.
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Paudel, Nava R. "Nanoparticle-aided Radiation Therapy: Micro-dosimetry and Evaluation of the Mediators Producing Biological Damage." University of Toledo / OhioLINK, 2014. http://rave.ohiolink.edu/etdc/view?acc_num=toledo1403142628.

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Books on the topic "Dosimeters – Evaluation"

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Holub, Robert F. Evaluation of the DOS1600 personal dosimeter. [Washington, D.C.?]: U.S. Dept. of the Interior, Bureau of Mines, 1995.

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Holub, Robert F. Evaluation of the DOS1600 personal dosimeter. [Washington, D.C.?]: U.S. Dept. of the Interior, Bureau of Mines, 1995.

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Zeman, G. H. Preliminary evaluation of U.S. Army RADIAC detector DT-236/PD and RADIAC computer-indicator CP-696/UD. Bethesda, Md: Defense Nuclear Agency, Armed Forces Radiobiology Research Institute, 1986.

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National Council on Radiation Protection and Measurements. The experimental basis for absorbed-dose calculations in medical uses of radionuclides: Recommendations of the National Council on Radiation Protection and Measurements. Bethesda, MD: The Council, 1985.

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O, Hŏn-jin. Inchʻe mohyŏng pʻaentʻŏm ŭl iyong han chʻiryo pangsasŏn sŏllyang pʻyŏngka =: Evaluation of the dose in radiotherapy using anthropomorphic phantom. [Seoul]: Sikpʻum Ŭiyakpʻum Anjŏnchʻŏng Ŭiryo Kigi Pʻyŏngkabu Pangsasŏn Pʻyojuntʻim, 2007.

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Chŏng, Chin-uk. Chungjaejŏk pangsasŏn punya esŏŭi hwanja pʻipʻok sŏllyang pʻyŏngka =: Evaluation of patient dose in interventional radiology. [Seoul]: Sikpʻum Ŭiyakpʻum Anjŏnchʻŏng, 2007.

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Office, General Accounting. Veterans' benefits: Training for claims processors needs evaluation : report to the Honorable Lane Evans, ranking democratic member, Committee on Veterans' Affairs, House of Representatives. Washington, D.C. (P.O. Box 37050, Washington 20013): The Office, 2001.

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Office, General Accounting. Veterans' benefits: Effective interaction needed within VA to address appeals backlog : report to Congressional requesters. Washington, D.C: The Office, 1995.

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Office, General Accounting. Veterans benefits: Acquisition of information resources for modernization is premature : report to the Chairman, Committee on Government Operations, House of Representatives. Washington, D.C: The Office, 1992.

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Office, General Accounting. Veterans' benefits: Basing survivors' compensation on veterans' disability is a viable option : report to Congressional committees. Washington, D.C: The Office, 1995.

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Book chapters on the topic "Dosimeters – Evaluation"

1

Petilli, M., and D. M. Gilliam. "Evaluation of Uncertainties of 235U Fission Spectrum." In Reactor Dosimetry, 657–65. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-5378-9_65.

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Petilli, M., and D. M. Gilliam. "Evaluation of Uncertainties of 235U Fission Spectrum." In Reactor Dosimetry, 657–65. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-010-9726-0_13.

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Lippincott, E. P., L. S. Kellogg, W. N. McElroy, and C. A. Baldwin. "Evaluation of Neutron Exposure Conditions for the Buffalo Reactor." In Reactor Dosimetry, 629–37. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-5378-9_62.

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Sakurai, K., and N. Yamano. "Evaluation of Gamma-Heating Rates in the JMTR Core." In Reactor Dosimetry, 667–80. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-5378-9_66.

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Lippincott, E. P., F. H. Ruddy, R. Gold, L. S. Kellogg, and J. H. Roberts. "Evaluation of Neutron Flux in the Pool Critical Assembly." In Reactor Dosimetry, 783–90. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-5378-9_78.

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Lippincott, E. P., L. S. Kellogg, W. N. McElroy, and C. A. Baldwin. "Evaluation of Neutron Exposure Conditions for the Buffalo Reactor." In Reactor Dosimetry, 629–37. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-010-9726-0_10.

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Lippincott, E. P., F. H. Ruddy, R. Gold, L. S. Kellogg, and J. H. Roberts. "Evaluation of Neutron Flux in the Pool Critical Assembly." In Reactor Dosimetry, 783–90. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-010-9726-0_26.

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Stallmann, F. W. "ORNL Evaluation of the ORR-PSF Metallurgical Experiment and “Blind Test." In Reactor Dosimetry, 175–83. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-5378-9_16.

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Sakurai, K., and N. Yamano. "Evaluation of Gamma-Heating Rates in the JMTR Core (Benchmark Calculation)." In Reactor Dosimetry, 667–80. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-010-9726-0_14.

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Simons, R. L., L. S. Kellogg, E. P. Lippincott, and W. N. McElroy. "Re-Evaluation of the Physics-Dosimetry from PWR and BWR Reactor Pressure Vessel Surveillance Programs." In Reactor Dosimetry, 165–73. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-5378-9_15.

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Conference papers on the topic "Dosimeters – Evaluation"

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Monteith, L. "97. Limitations of Weight Change Technique for Evaluation of Passive Dosimeters." In AIHce 1999. AIHA, 1999. http://dx.doi.org/10.3320/1.2763418.

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Tsuchiya, K., K. Kuroki, K. Kurosawa, N. Akiba, K. Tonoike, G. Uchiyama, Y. Miyoshi, et al. "Evaluation of personal dosimeters and electronic modules under high-dose field." In 2010 IEEE Nuclear Science Symposium and Medical Imaging Conference (2010 NSS/MIC). IEEE, 2010. http://dx.doi.org/10.1109/nssmic.2010.5873812.

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Mukherjee, Bhaskar. "Further evaluation of neutron skyshine dose in vicinity of the K1200 superconducting cyclotron of the NSCL using bubble dosimeters." In CYCLOCTRONS AND THEIR APPLICATIONS 2001: Sixteenth International Conference. AIP, 2001. http://dx.doi.org/10.1063/1.1435209.

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Chung, C., M. Morandi, M. Afshar, and T. Stock. "65. Test Chamber and Protocol for the Evaluation of Passive Dosimeters at Sub-PPM Concentrations of VOCs with 24-Hour Sampling." In AIHce 1996 - Health Care Industries Papers. AIHA, 1999. http://dx.doi.org/10.3320/1.2765177.

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Wester, Ulf. "Polysulphone and spore-film UV-dosimeters compared to two radiation transfer models and an instrument that measures the UV index: an evaluation for a UV-dosimetry study of preschool children in Stockholm." In Remote Sensing, edited by James R. Slusser, Klaus Schäfer, and Adolfo Comerón. SPIE, 2006. http://dx.doi.org/10.1117/12.690014.

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Lee, SamLai, ByoungChul Kim, ChoonSung Yoo, and KeeOk Chang. "Monitoring of a Radiation Embrittlement by a Reliable Fluence Evaluation With a Neutron Dosimetry in a Reactor Pressure Vessel." In ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference. ASMEDC, 2006. http://dx.doi.org/10.1115/pvp2006-icpvt-11-93500.

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The assurance of a nuclear reactor pressure vessel integrity plays an important role in achieving a safety and extending the life of nuclear power plants. In the assessment of the state of an embrittlement of a pressure vessel in a pressurized light water reactor, an accurate evaluation of the neutron exposure of each of the materials comprising the beltline region of the vessel is required. The evaluation is performed through a neutron dosimetry analysis where a fluence calculation is done by both measurement of the dosimeter materials removed from surveillance capsules and a neutron transport calculation. Now that all the capsules have been completely removed from the reactor vessel and analyzed by a periodic monitoring schedule, four ex-vessel sensor sets are installed as a substitute capsule in an axial direction in the reactor cavity and then removed for an analysis in order to meet the regulation requirements. The results showed that the differences between the measurements and calculations are less than 20% for each capsule, which means these analyses satisfy the acceptable criterion required by Regulatory Guide 1.190, and they also provide an assurance that such an evaluation including an ex-vessel neutron dosimetry can be used to predict the fluence of a nuclear reactor vessel with a good reliability.
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Ballesteros, A., J. Bros, L. Debarberis, F. Sevini, D. Erak, S. Gezashchenko, A. Kryukov, et al. "Assessment of Irradiation Conditions in WWER-440 (213) RPV Surveillance Location." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49477.

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The key component of WWER is the Reactor Pressure Vessel (RPV). The evaluation and prognosis of RPV material embrittlement and the allowable period of its safe operation are performed on the basis of impact test results of irradiated surveillance specimens (SS). The main problem is that the SS irradiation conditions (temperature of SS, neutron flux and neutron spectrum) have not been determined yet with the necessary accuracy. These conditions could differ from the actual RPV condition. In particular, the key issue is the possible difference between the irradiation temperature of the SS and the actual RPV temperature. It is recognized that the direct measurement of temperature by thermocouples during reactor operation is the only way for receiving reliable information. In addition, the neutron field’s parameters for surveillance specimens have not been determined yet with the necessary accuracy. The use of state of the art dosimeters can provide high accuracy in the determination of the neutron exposure level. The COBRA project (http://ie.jrc.cec.eu.int/ames/), which started in August 2000 and had a duration of three years, was designed to solve the above-mentioned problems. Surveillance capsules were manufactured which contain state of art dosimeters and temperature monitors (melting alloys). In addition, thermocouples were installed throughout the instrumentation channels of the vessel head to measure directly the irradiation temperature in the surveillance position during the reactor operation. The selected reactor was the Unit 3 of Kola NPP situated in the arctic area of Russia. Irradiation of the capsules and online temperature measurements were performed during one fuel cycle. On the base of statistical processing of thermocouples readings the temperature of irradiated surveillance specimens in WWER-440/213 reactor can be accepted as 269.5±4°C. The results obtained show that there is not need in temperature correction when data of surveillance specimens studies are used for assessment of WWER-440/213 reactor pressure vessels. Maximum neutron flux evaluated using detectors, which were placed in the Charpy specimen simulators, equals ∼2.7·1012 cm−2s−1 with E&gt;0.5 MeV. It is established that depending on the orientation of the capsules with respect to the core, the detectors of the standard surveillance capsules can give both overestimated and underestimated neutron flux values, as compared to the actual flux received by the surveillance specimens. The overestimation or underestimation can reach 10%.
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Zhou, Chuanyu. "A Deterministic Approach to Brachytherapy Dosimetry and a Benchmark Problem Implementation." In QUANTITATIVE NONDESTRUCTIVE EVALUATION. AIP, 2004. http://dx.doi.org/10.1063/1.1711671.

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Hopkins, Daniel N., Eugene T. Hayes, and Arnold H. Ferro. "Ex-Vessel Neutron Dosimetry Results in the Vicinity of RPV Supports." In ASME 2007 Pressure Vessels and Piping Conference. ASMEDC, 2007. http://dx.doi.org/10.1115/pvp2007-26785.

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Neutron-induced embrittlement of the reactor pressure vessel has been a long standing concern for pressurized water reactors (PWR). To date, the beltline region of the pressure vessel, defined as the portion of the pressure vessel experiencing fast neutron fluence (E &gt; 1.0 MeV) equal to or greater than 1017 n/cm2, has been the primary focus of evaluations assessing this embrittlement. These evaluations typically include a calculation of the neutron flux incident on the reactor pressure vessel beltline region, which is in part validated by direct comparison with dosimetry measurements. Two general types of measurements are commonly used, those being dosimetry sets that are included as part of the in-vessel surveillance capsules, and at some plants, those that are included in supplemental surveillance programs such as Ex-Vessel Neutron Dosimetry. In the context of life extension, the beltline region as defined above is getting larger. Present fluence calculations for a number of plants indicate that beltline region at the end of the 60 years of operation will extend to the bottom of the reactor pressure vessel nozzle welds. This extended beltline creates a new problem in terms of validating the neutron fluence calculations in this region well above the top of the active fuel, in that there are no measurements available to confirm calculated results in this new region of interest. Prior to the start-up of Cycle 11 at Comanche Peak Unit 1, an Ex-Vessel Neutron Dosimetry Program was initiated. This program included placement of neutron dosimetry sensor sets in the vicinity of the reactor pressure vessel supports. At the conclusion of Cycle 11, the first set of dosimetry was replaced and the irradiated set analyzed. The Ex-Vessel Neutron Dosimetry set from Cycle 11 was analyzed using a 2D/1D flux synthesis technique using the two dimensional discrete ordinates transport theory calculations (DORT) along with the BUGLE 96 cross-section library and the SNLRML neutron dosimetry cross-section library. The measurements in the vicinity of the vessel supports compare well with the transport calculations, thus confirming that the expected fast neutron fluence (E &gt; 1.0 MeV) in the vicinity of the reactor vessel supports is below the 1018 n/cm2.
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Durkt, George. "Reducing the Noise Generated During Air-Arc Gouging Can Be as Simple as Flipping a Switch." In ASME 2009 International Mechanical Engineering Congress and Exposition. ASMEDC, 2009. http://dx.doi.org/10.1115/imece2009-12830.

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The Mine Safety and Health Administration (MSHA) has been evaluating the job/task of air-arc gouging performed by mine shop welders. Air-arc gouging is the process of melting an old weld with a carbon based electrode (rod) and blowing the molten metal away with compressed air. Noise levels of 115 dBA or higher can be generated in this process. Three acoustical field evaluations were conducted at mine shops comparing both Constant Current (CC) and Constant Voltage (CV) techniques for air-arc gouging. The results indicate that by using the CV technique, the average overall A-Weighted Sound Pressure Level (SPLA) was reduced by as much as 8 dBA from an average of 117.6 dBA to 109.3 dBA. As might be expected, dosimeter results indicated that the rate of noise accumulation was also reduced utilizing the CV technique. The average accumulation rate decreased from 4.5 percent Dose per minute for CC at varying air pressures to 2.0 percent Dose per minute for CV at 80 psig.
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Reports on the topic "Dosimeters – Evaluation"

1

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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Hickman, D., A. Wysong, D. Heinrichs, C. Wong, M. Merritt, J. Topper, F. Gressmann, and D. Madden. Evaluation of LLNL's Nuclear Accident Dosimeters at the CALIBAN Reactor September 2010. Office of Scientific and Technical Information (OSTI), June 2011. http://dx.doi.org/10.2172/1033328.

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Gunter, R. J. Evaluation of the neutron dosimeter used by Martin Marietta Energy Systems, Inc., ability to meet the requirements of the American National Standard for Personnel Neutron Dosimeters (neutron energies less than 20 MeV) ANSI N319-1976. Office of Scientific and Technical Information (OSTI), July 1994. http://dx.doi.org/10.2172/10163873.

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Herminghuysen, Kevin Ryan. Development and evaluation of a neutron-gamma mixed-field dosimetry system based on a single thermoluminescence dosimeter. Office of Scientific and Technical Information (OSTI), January 1993. http://dx.doi.org/10.2172/10188779.

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Shaw, K. R. Evaluation of discrepancies between thermoluminescent dosimeter and direct-reading dosimeter results. Office of Scientific and Technical Information (OSTI), July 1993. http://dx.doi.org/10.2172/10177407.

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Kinnison, R. Evaluation of environmental monitoring thermoluminescent dosimeter locations. Office of Scientific and Technical Information (OSTI), December 1992. http://dx.doi.org/10.2172/138636.

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Heaton, H. T. II. Evaluation of NVLAP personnel dosimetry testing laboratory:. Gaithersburg, MD: National Institute of Standards and Technology, 1990. http://dx.doi.org/10.6028/nist.ir.90-4299.

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Piper, Roman K., and Robert I. Scherpelz. Functional Evaluation of the DOZA DKG-05D Electronic Dosimeter System. Office of Scientific and Technical Information (OSTI), November 2009. http://dx.doi.org/10.2172/969177.

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Johnson, M. L. Evaluation of the Science Applications International Corporation PD-4 electronic dosimeter. Office of Scientific and Technical Information (OSTI), November 1993. http://dx.doi.org/10.2172/10110203.

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Cummings, F. M., D. L. Haggard, and G. W. R. Endres. Evaluation of neutron dosimetry techniques for well-logging operations. Office of Scientific and Technical Information (OSTI), July 1985. http://dx.doi.org/10.2172/5399666.

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