AbstractAbstract
[en] Arachnoid granulations are structures filled with cerebrospinal fluid (CSF) that extend into the venous sinuses through openings in the dura mater and allow the drainage of CSF from subarachnoid space into venous system. Usually they are asymptomatic but can be symptomatic when large enough to cause sinus occlusion. We report a rare case of a brain herniation into a giant arachnoid granulation in an asymptomatic elderly male patient, which was discovered incidentally
Primary Subject
Source
Country of input: Egypt
Record Type
Journal Article
Journal
Case Reports in Radiology; ISSN 2090-6870; ; v. 2017(2017); 4 p
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Santos, G. R. T.; Durazzo, M.; Carvalho, E. F. U.; Riella, H. G., E-mail: grsantos@ipen.br
Sociedad Nuclear Mexicana (SNM), Mexico D.F. (Mexico); Comision Federal de Electricidad (Mexico); Comision Nacional de Seguridad Nuclear y Salvaguardias (Mexico); Instituto de Investigaciones Electricas (Mexico); Instituto Nacional de Investigaciones Nucleares (Mexico); Instituto Politecnico Nacional (Mexico); Universidad Autonoma de Zacatecas (Mexico); Universidad Nacional Autonoma de Mexico (Mexico); Academia de Ingenieria de Mexico (Mexico); Asociacion de Jovenes por la Energia Nuclear en Mexico (Mexico); Secretaria de Fomento Turistico, Gobierno del Estado de Yucatan (Mexico). Funding organisation: Areva (France); Bartlett de Mexico (Mexico); GE Energy (United States); Grupo IAI (Mexico); Iberdrola (Spain); Nukem (Germany); Tenex (Russian Federation); Vertek (United States); Westinghouse (United States)2008
Sociedad Nuclear Mexicana (SNM), Mexico D.F. (Mexico); Comision Federal de Electricidad (Mexico); Comision Nacional de Seguridad Nuclear y Salvaguardias (Mexico); Instituto de Investigaciones Electricas (Mexico); Instituto Nacional de Investigaciones Nucleares (Mexico); Instituto Politecnico Nacional (Mexico); Universidad Autonoma de Zacatecas (Mexico); Universidad Nacional Autonoma de Mexico (Mexico); Academia de Ingenieria de Mexico (Mexico); Asociacion de Jovenes por la Energia Nuclear en Mexico (Mexico); Secretaria de Fomento Turistico, Gobierno del Estado de Yucatan (Mexico). Funding organisation: Areva (France); Bartlett de Mexico (Mexico); GE Energy (United States); Grupo IAI (Mexico); Iberdrola (Spain); Nukem (Germany); Tenex (Russian Federation); Vertek (United States); Westinghouse (United States)2008
AbstractAbstract
[en] The aim of the industrial activities success, front to a more and more informed and demanding society and to a more and more competitive market demands an environmental administration policy which doesn't limit itself to assist the legislation but anticipate and prevent, in a responsible way, possible damages to the environment. One of the maim programs of the Institute of Energetic and Nuclear Research of the national Commission of Nuclear Energy located in Brazil, through the Center of Nuclear Fuel - CCN - is to manufacture MTR-type fuel elements using low-enrichment uranium (20 wt% 235U), to supply its IEA-RI research reactor. Integrated in this program, this work aims at well developing and assuring a methodology to implant an environment, health and safety policy, foreseeing its management with the use of detailed data reports and through the adoption of new tools for improving the management, in order to fulfil the applicable legislation and accomplish all the environmental, operational and works aspects. The applied methodology for the effluents management comprises different aspects, including the specific environmental legislation of a country, main available effluents treatment techniques, process flow analyses from raw materials and intakes to products, generated effluents, residuals and emissions. Data collections were accomplished for points gathering and tests characterization, classification and compatibility of the generated effluents and their eventual environmental impacts. This study aims to implant the Sustainable Concept in order to guarantee access to financial resources, allowing cost reduction, maximizing long-term profits, preventing and reducing environmental accident risks and stimulating both the attraction and the keeping of a motivated manpower. Work on this project has already started and, even though many technical actions have not still ended, the results have being extremely valuable. These results can already give to CCN/IPEN-CNEN more efficiency concerning financial and environmental aspects. This work will surely contribute to the sustainable of our enterprise, assuring the growth of CCN in economically viable, socially fair and environmental responsible way. (Author)
Original Title
Atomos para el desarrollo de Mexico
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Secondary Subject
Source
2008; 12 p; 19. Annual SNM Congress; Atoms for the development of Mexico; Merida, Yuc. (Mexico); 6-9 Jul 2008; ISBN 978-968-9353-01-1; ; Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion Nuclear, 52045 Ocoyoacac, Estado de Mexico (MX). e-mail: svp@nuclear.inin.mx; rbc@nuclear.inin.mx
Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
Country of publication
BRAZILIAN CNEN, CHEMICAL EFFLUENTS, COMPILED DATA, ENRICHED URANIUM, ENVIRONMENTAL IMPACTS, ENVIRONMENTAL POLICY, FILTRATION, FUEL ELEMENTS, GOVERNMENT POLICIES, IEAR-1 REACTOR, ISOTOPE SEPARATION, NUCLEAR ENERGY, NUCLEAR FUELS, RADIOACTIVE EFFLUENTS, RADIOACTIVE WASTE PROCESSING, RESEARCH REACTORS, WASTE RETRIEVAL
ACTINIDES, BRAZILIAN ORGANIZATIONS, CHEMICAL WASTES, DATA, ELEMENTS, ENERGY, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, GOVERNMENT POLICIES, INFORMATION, ISOTOPE ENRICHED MATERIALS, MANAGEMENT, MATERIALS, METALS, NATIONAL ORGANIZATIONS, NONRADIOACTIVE WASTES, NUMERICAL DATA, POOL TYPE REACTORS, PROCESSING, RADIOACTIVE MATERIALS, RADIOACTIVE WASTE MANAGEMENT, RADIOACTIVE WASTES, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SEPARATION PROCESSES, THERMAL REACTORS, URANIUM, WASTE MANAGEMENT, WASTE PROCESSING, WASTES, WATER COOLED REACTORS, WATER MODERATED REACTORS
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AbstractAbstract
[en] Purpose: Several studies have reported methodologies to calculate and correct the transit dose component of the moving radiation source for high dose rate (HDR) brachytherapy planning systems. However, most of these works employ the average source speed, which varies significantly with the measurement technique used, and does not represent a realistic speed profile, therefore, providing an inaccurate dose determination. In this work, the authors quantified the transit dose component of a HDR unit based on the measurement of the instantaneous source speed to produce more accurate dose values. Methods: The Nucletron microSelectron-HDR Ir-192 source was characterized considering the Task Group 43 (TG-43U1) specifications. The transit dose component was considered through the calculation of the dose distribution using a Monte Carlo particle transport code, MCNP5, for each source position and correcting it by the source speed. The instantaneous source speed measurements were performed in a previous work using two optical fibers connected to a photomultiplier and an oscilloscope. Calculated doses were validated by comparing relative dose profiles with those obtained experimentally using radiochromic films. Results: TG-43U1 source parameters were calculated to validate the Monte Carlo simulations. These agreed with the literature, with differences below 1% for the majority of the points. Calculated dose profiles without transit dose were also validated by comparison with ONCENTRA® Brachy v. 3.3 dose values, yielding differences within 1.5%. Dose profiles obtained with MCNP5 corrected using the instantaneous source speed profile showed differences near dwell positions of up to 800% in comparison to values corrected using the average source speed, but they are in good agreement with the experimental data, showing a maximum discrepancy of approximately 3% of the maximum dose. Near a dwell position the transit dose is about 22% of the dwell dose delivered by the source dwelling 1 s and reached 104.0 cGy per irradiation in a hypothetical clinical case studied in this work. Conclusions: The present work demonstrated that the transit dose correction based on average source speed fails to accurately correct the dose, indicating that the correct speed profile should be considered. The impact on total dose due to the transit dose correction near the dwell positions is significant and should be considered more carefully in treatments with high dose rate, several catheters, multiple dwell positions, small dwell times, and several fractions.
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Source
(c) 2013 American Association of Physicists in Medicine; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Country of publication
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CALCULATION METHODS, DAYS LIVING RADIOISOTOPES, ELECTRON CAPTURE RADIOISOTOPES, FIBERS, HEAVY NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, IRIDIUM ISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MEDICINE, MINUTES LIVING RADIOISOTOPES, NUCLEAR MEDICINE, NUCLEI, ODD-ODD NUCLEI, RADIOISOTOPES, RADIOLOGY, RADIOTHERAPY, SIMULATION, THERAPY, YEARS LIVING RADIOISOTOPES
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