No description available.

O consumo de tabaco é uma das principais causas de doenças e morte prematuras no mundo; é a segunda droga mais consumida entre os adolescentes brasileiros, sendo considerado uma importante porta de entrada para o uso de drogas ilícitas. O Brasil é o segundo produtor mundial de tabaco e desde de 1993 destaca-se como o maior exportador. Os radionuclídeos naturais das séries do 232Th e 238U são encontrados no tabaco em baixas concentrações absorvidos diretamente do solo ou por deposição foliar. No ato de fumar ocorre a transferência desses radionuclídeos através da queima do tabaco para os tecidos e órgãos humanos podendo gerar lesões cancerígenas, sendo o mais relevante o câncer de pulmão. Existem poucos dados sobre a caracterização radiológica e elementar dos derivados do tabaco brasileiros, o que torna relevante o presente estudo que teve como objetivos a determinação da radioatividade natural e da concentração de elementos maiores e traços em derivados de tabaco produzidos e comercializados no Brasil. As técnicas analíticas empregadas foram alfa e beta total após separação radioquímica para os radionuclídeos 226Ra, 228Ra e 210Pb com determinação em detector proporcional de fluxo gasoso e baixa radiação de fundo, espectrometria alfa após separação radioquímica para o radionuclídeo 210Po, análise por ativação com nêutrons instrumental (INAA) e fluorescência por dispersão de raios X (EDXRF) para determinação de 238U, 232Th, elementos maiores e traços. Foram analisados produtos derivados da Nicotina tabacum L. de diferentes marcas adquiridas em tabacarias: cigarro não aromatizados, cigarro aromatizado, charuto, rapé, cigarro de palha e fumo de corda. Pela técnica de INAA foi possível determinar a concentração de 19 elementos e pela técnica de EDXRF de 31 elementos o que possibilitou uma ampla caracterização multielementar e as técnicas analíticas empregadas se mostraram complementares. Os elementos que apresentaram maiores valores de concentração foram o Ca e o K entre todas as amostras amostragem e entre todos os radionuclídeos naturais determinados o 228Ra apresentou maiores valores de concentração de atividade. A partir da concentração de atividade determinada foram calculadas a dose anual estimada e a dose anual efetiva para os radionuclídeos 210Pb e 210Po, levando-se em consideração um consumo anual de 3,65 kg de tabaco por ano. A dose anual efetiva variou de 69,5 μSv ano-1 à 121 μSv ano-1. Os produtos que apresentaram maiores valores de concentração e consequentemente maiores valores de dose anual efetiva, para a maioria dos radionuclídeos analisados, foram os cigarros de palha e fumos de corda. / Tobacco use is one of the leading causes of premature illness and death in the world; is the second most consumed drug among Brazilian adolescents, being considered an important gateway to the use of illicit drugs. Brazil is the second largest tobacco producer in the world and since 1993 it has been the largest exporter. The natural radionuclides from the 232Th and 238U series are found in tobacco at low concentrations absorbed directly from the soil or by foliar deposition. In the act of smoking occurs the transference of these radionuclides through the burning of the tobacco to the human tissues and organs and they can generate carcinogenic lesions, being the lung cancer the most relevant. There are few data on the elemental and radiological characterization of Brazilian tobacco products, which makes relevant the present study that had as objectives the determination of the natural radioactivity and the concentration of major and trace elements in tobacco products produced and marketed in Brazil. The analytical techniques employed were gross alpha and beta, after radiochemical separation for the radionuclides 226Ra, 228Ra and 210Pb with determination in a gaseous flow proportional detector of low background radiation, alpha spectrometry after radiochemical separation for the radionuclide 210Po, instrumental neutron activation analysis (INAA) and X-ray scattering fluorescence (EDXRF) for determination of 238U, 232Th, major and trace elements. Nicotine tabacum L. products from different brands acquired in cigar stores were analyzed: non-flavored cigarettes, flavored cigarettes, cigar, snuff, straw cigarettes and rope smoke. Using the INAA technique, it was possible to determine the concentration of 19 elements and with the EDXRF technique 31 elements, which enabled a wide multielementar characterization; the analytical techniques employed were complementary. The elements that presented the highest concentration values were Ca and K among all the samples and among all the natural radionuclides determined the 228Ra presented higher values of activity concentration. The estimated annual dose and annual effective dose for the 210Pb and 210Po radionuclides were calculated from the determined activity concentration, taking into account an annual consumption of 3.65 kg of tobacco per year. The effective annual dose ranged from 69.5 μSv y-1 to 121 μSv y-1. The products with the highest concentration values and hence the highest annual effective dose for the majority of the radionuclides analyzed were straw cigarettes and rope smoke.

O consumo de tabaco é uma das principais causas de doenças e morte prematuras no mundo; é a segunda droga mais consumida entre os adolescentes brasileiros, sendo considerado uma importante porta de entrada para o uso de drogas ilícitas. O Brasil é o segundo produtor mundial de tabaco e desde de 1993 destaca-se como o maior exportador. Os radionuclídeos naturais das séries do 232Th e 238U são encontrados no tabaco em baixas concentrações absorvidos diretamente do solo ou por deposição foliar. No ato de fumar ocorre a transferência desses radionuclídeos através da queima do tabaco para os tecidos e órgãos humanos podendo gerar lesões cancerígenas, sendo o mais relevante o câncer de pulmão. Existem poucos dados sobre a caracterização radiológica e elementar dos derivados do tabaco brasileiros, o que torna relevante o presente estudo que teve como objetivos a determinação da radioatividade natural e da concentração de elementos maiores e traços em derivados de tabaco produzidos e comercializados no Brasil. As técnicas analíticas empregadas foram alfa e beta total após separação radioquímica para os radionuclídeos 226Ra, 228Ra e 210Pb com determinação em detector proporcional de fluxo gasoso e baixa radiação de fundo, espectrometria alfa após separação radioquímica para o radionuclídeo 210Po, análise por ativação com nêutrons instrumental (INAA) e fluorescência por dispersão de raios X (EDXRF) para determinação de 238U, 232Th, elementos maiores e traços. Foram analisados produtos derivados da Nicotina tabacum L. de diferentes marcas adquiridas em tabacarias: cigarro não aromatizados, cigarro aromatizado, charuto, rapé, cigarro de palha e fumo de corda. Pela técnica de INAA foi possível determinar a concentração de 19 elementos e pela técnica de EDXRF de 31 elementos o que possibilitou uma ampla caracterização multielementar e as técnicas analíticas empregadas se mostraram complementares. Os elementos que apresentaram maiores valores de concentração foram o Ca e o K entre todas as amostras amostragem e entre todos os radionuclídeos naturais determinados o 228Ra apresentou maiores valores de concentração de atividade. A partir da concentração de atividade determinada foram calculadas a dose anual estimada e a dose anual efetiva para os radionuclídeos 210Pb e 210Po, levando-se em consideração um consumo anual de 3,65 kg de tabaco por ano. A dose anual efetiva variou de 69,5 μSv ano-1 à 121 μSv ano-1. Os produtos que apresentaram maiores valores de concentração e consequentemente maiores valores de dose anual efetiva, para a maioria dos radionuclídeos analisados, foram os cigarros de palha e fumos de corda. / Tobacco use is one of the leading causes of premature illness and death in the world; is the second most consumed drug among Brazilian adolescents, being considered an important gateway to the use of illicit drugs. Brazil is the second largest tobacco producer in the world and since 1993 it has been the largest exporter. The natural radionuclides from the 232Th and 238U series are found in tobacco at low concentrations absorbed directly from the soil or by foliar deposition. In the act of smoking occurs the transference of these radionuclides through the burning of the tobacco to the human tissues and organs and they can generate carcinogenic lesions, being the lung cancer the most relevant. There are few data on the elemental and radiological characterization of Brazilian tobacco products, which makes relevant the present study that had as objectives the determination of the natural radioactivity and the concentration of major and trace elements in tobacco products produced and marketed in Brazil. The analytical techniques employed were gross alpha and beta, after radiochemical separation for the radionuclides 226Ra, 228Ra and 210Pb with determination in a gaseous flow proportional detector of low background radiation, alpha spectrometry after radiochemical separation for the radionuclide 210Po, instrumental neutron activation analysis (INAA) and X-ray scattering fluorescence (EDXRF) for determination of 238U, 232Th, major and trace elements. Nicotine tabacum L. products from different brands acquired in cigar stores were analyzed: non-flavored cigarettes, flavored cigarettes, cigar, snuff, straw cigarettes and rope smoke. Using the INAA technique, it was possible to determine the concentration of 19 elements and with the EDXRF technique 31 elements, which enabled a wide multielementar characterization; the analytical techniques employed were complementary. The elements that presented the highest concentration values were Ca and K among all the samples and among all the natural radionuclides determined the 228Ra presented higher values of activity concentration. The estimated annual dose and annual effective dose for the 210Pb and 210Po radionuclides were calculated from the determined activity concentration, taking into account an annual consumption of 3.65 kg of tobacco per year. The effective annual dose ranged from 69.5 μSv y-1 to 121 μSv y-1. The products with the highest concentration values and hence the highest annual effective dose for the majority of the radionuclides analyzed were straw cigarettes and rope smoke.

Orientador: Diana Rodrigues Pina / Resumo: A Radiologia Intervencionista (RI) é a área da medicina que proporciona as maiores exposições ocupacionais. Os valores de dose aos quais os intervencionistas são expostos são difíceis de padronizar. Nesta pesquisa apresentamos uma avaliação completa das exposições ocupacionais e determinamos a eficiência de distintos métodos de dosimetria pessoal utilizados na RI. Essa pesquisa foi abordada em 2 etapas, conforme descrito a seguir: A primeira etapa se baseou em caracterizar as exposições ocupacionais em diferentes modalidades de procedimentos de RI vascular para duas categorias de profissionais e estimar o número de procedimentos anuais que cada profissional pode realizar sem exceder os limites de dose. Foi avaliada a exposição ocupacional, através de dosimetria termoluminescente, em diferentes partes do corpo (cristalino, tireoide, tórax, abdômen, pés e mãos) de duas categorias de intervencionistas (principais e assistentes) em três modalidades diferentes de procedimentos de RI vascular. As maiores doses equivalentes foram encontradas para as mão de ambos os profissionais, podendo chegar a aproximadamente 9 mSv em um único procedimento. Algumas regiões dos profissionais em alguns procedimentos podem receber, durante o ano, níveis de doses perigosamente perto dos limites anuais. Dosímetros posicionados no tórax podem subestimar as doses para outras regiões do corpo, especialmente abdômen, extremidades e cristalinos. Na segunda etapa foram avaliadas as eficiências de 6 diferent... (Resumo completo, clicar acesso eletrônico abaixo) / Abstract: Interventional Radiology (IR) is the area of medicine that provides the largest occupational exposures. The dose values to which interventionists are exposed are difficult to standardize. In this research we present a complete evaluation of occupational exposures and determine the efficiency of different personal dosimetry methods used in IR. This research was performed in 2 stages, as described below: The first step was to characterize the occupational exposures in different modalities of vascular IR procedures for two categories of professionals. We also estimated the number of annual procedures that each professional can perform without exceeding the dose limits. Occupational exposures were evaluated in different body parts (crystalline, thyroid, thorax, abdomen, feet and hands) by two interventional categories (primary and assistants) in three different modalities of vascular IR procedures. The highest equivalent doses were found for the hands of both professionals, reaching approximately 9 mSv in a single procedure. Some regions of professionals in some procedures may receive dose levels during the year dangerously close to annual limits. Dosimeters positioned in the chest may underestimate the doses to other regions of the body, especially the abdomen, extremities and crystalline. The second stage, we evaluated the efficiencies of 6 different personal dosimetry methodologies used internationally to estimate the effective dose received by interventional professionals. An... (Complete abstract click electronic access below) / Mestre

The practice in the department of nuclear medicine requires the involvement of radiation protection with care of patients and occupational safety of radiation workers. Nuclear medicine involves the handling of radioactive substances that may cause external or internal irradiation of workers. The amount of the dose depends on the type of radionuclide, the amount of energy, the work performed by the worker within the department. Patients or staff may be exposed to the external or internal irradiation. The topic of this thesis is the analysis of the current state of radiation protection in the department of nuclear medicine according to the new legislation. The part of the work is the evaluation of monitoring of workers and patients. The research results of the average annual effective dose of total body irradiation at radiation workers ranged from 1.35 to 1.73 mSv, monthly ranged from 0.1? 0.65 mSv. The average annual equivalent dose of Hp (0,07) ranged from 1.15 to 117.68 mSw. The lowest monthly Hp (0.07) was 0.07 mSw and the highest one was 19.92 mSw. At SSK-treated patients the doses applied were 4% lower than diagnostic reference level and the dose at DSSL-treated patients was 22% less than DRU. In conclusion, it was found that the values from personal dosimeters were below the limit and in the case of finger dosimeters in two cases the values were above the examination level. The values of other workers were below the monitoring level during the monitored period. The applied doses of radiopharmaceuticals were less in the observed group of patients than the established diagnostic reference level. On the basis of the presented results it can be stated that radiation protection is in the Department of Nuclear Medicine of Znojmo Hospital f.o, secured in accordance with the applicable legislation.

Radioactive seed implant brachytherapy is a common radiotherapy treatment method for prostate cancer. In current clinical practice, a seed consists of a single isotope, such as 125I or 103Pd. A seed containing a mixture of two isotopes has been proposed for prostate cancer treatment. This study investigates a method for defining a prescription dose for new seed compositions based on matching the biological equivalent dose (BED) of a reference plan. Ten prostate cancer cases previously treated using single isotope seeds (5 using 125I seeds and 5 using 103Pd seeds) were selected for this study. Verification of the method was done by calculating prescription doses for 103Pd and 125I seeds. A prescription dose for a 50/50 hybrid seed was calculated. Number and location of seeds remained invariant within each case. The BED distributions for hybrid and single isotope seed plans were generated and matched to the BED distribution generated off of the optimized plans. For the 125I isotopes, the dose necessary to cover 90% of the prostate with a BED of 110 Gy is 145 Gy. For the same BED coverage, the dose for 103Pd and 50/50 hybrid seed is 120 Gy and 137 Gy respectively. A method is introduced for obtaining prescription doses for new brachytherapy sources. The method was verified by obtaining doses for 125I and 103Pd isotopes which match clinical prescription doses. The method developed is robust enough to calculate prescription doses in any region of interest, for any seed type, and for any isotope as long as the BED coverage remains invariant with respect to the treatment plan. Numerical calculations were performed to derive analytical conversions of total dose to BED for 50/50, 75/25 and 25/75 hybrid seeds. These analytical conversions are faster than the original numerical methods employed allowing for real-time BED optimization for hybrid seeds. Varying seed distribution was seen not to influence the analytical conversions. It was observed that when total dose remained invariant while individual isotope contributions varied, the value of BED varied. The BED variance was seen to be the smaller at larger BED values (~2% at 100 Gy). Using the conversions derived in this paper, BED based optimization for hybrid seeds are now performable. However, these conversions should only be used in high dose regions due to high uncertainty in the low regime.

Abstract Fluoroscopically guided procedures are currently an area of special concern in relation to radiation protection, as they may produce a high radiation dose to patients and increase the risk of skin injury. ERCP is a gastrointestinal procedure used as a gold standard in the treatment of pancreatobiliary disorders. It is performed under endoscopic and fluoroscopic guidance. Recently, both the number and the complexity with associated increased technical difficulty of therapeutic ERCP procedures have significantly increased. The present study aimed to assess the medical use of radiation in ERCP, with special emphasis on optimisation of radiation protection of patients. For this purpose, the level of patient radiation exposure during ERCP was evaluated by registering the radiation dose indices in Finnish hospitals. The entrance surface dose was measured by thermoluminescent dosimeters and the effective dose was estimated using conversion coefficients. For dose optimisation and for quality assurance, the local diagnostic reference levels (DRL) for ERCP were established and reviewed after five years. A single centre prospective analysis was conducted to identify patient-, procedure- and operator-related factors affecting dose area product (DAP) and fluoroscopy time (FT). The results showed a large variation of dose indices in overall, as among participating hospitals due to differences in patient characteristics, operator, equipment and procedural complexity. The risk of radiation-induced skin injury and the lifetime cancer risk seems to be reasonably low, indicating ERCP to be a low-dose study. Local DRL is an effective tool in the optimisation process, as a certain degree of dose reduction was achieved during the years. Multiple factors were found to affect DAP and FT in ERCP. The awareness of these factors may help to predict possible prolonged procedures that cause a higher radiation dose to the patient and thus facilitate the use of appropriate precautions. / Tiivistelmä Säteilysuojelun näkökulmasta läpivalaisuohjauksessa tehtävät toimenpiteet ovat erityisen huolen aiheena, koska ne voivat aiheuttaa potilaille suuria säteilyannoksia ja siten lisätä ihovaurion riskiä. ERCP on ruoansulatuskanavan endoskopiatoimenpide, jota käytetään haima- ja sappitiesairauksien hoidossa kultaisena standardina. ERCP suoritetaan duodenoskoopilla läpivalaisukontrollissa. Viime vuosina ERCP toimenpiteiden määrät ja toimenpiteiden monimutkaisuus ovat kasvaneet merkittävästi lisääntyneen teknisen haastavuuden vuoksi. Tutkimuksen tarkoituksena oli arvioida säteilyn lääketieteellistä käyttöä ERCP:ssa, kiinnittäen eritystä huomiota potilaan säteilysuojelun optimointiin. Potilaan säteilyaltistuksen tasoa ERCP:ssa arvioitiin keräämällä potilasannoksia suomalaisista sairaaloista, pinta-annokset mitattiin termoloistedosimetreilla ja efektiivinen annos laskettiin muuntokertoimilla. Säteilyaltistuksen optimointi- ja laadunvalvonnan työkaluksi ERCP:lle asetettiin paikalliset vertailutasot ja ne tarkistettiin 5 vuoden kuluttua. Potilaaseen, toimenpiteeseen ja toimenpiteen suorittajaan liittyvät tekijät, jotka vaikuttavat annoksen ja pinta-alan tuloon (DAP) sekä läpivalaisuaikaan, selvitettiin retrospektiivisesti yhdessä sairaalassa. Tutkimuksen tulokset osoittivat, että potilaan säteilyannoksissa oli suurta vaihtelua niin yleisesti, kuin osallistuvien sairaaloiden välillä. Vaihtelu johtui potilaan ominaisuuksista, erilaisista läpivalaisulaitteista, toimenpiteen suorittajista ja ERCP toimenpiteiden vaikeusasteesta. Säteilyn aiheuttaman ihovaurion riski ja elinikäinen syöpäriski näyttäisi tulosten perusteella olevan kohtuullisen alhainen, mikä osoittaa, että ERCP on matala-annostutkimus. Paikallinen vertailutaso osoittautui tehokkaaksi optimointityökaluksi, sillä annostason lasku ERCP:ssa saavutettiin vuosien kuluessa. Useiden tekijöiden todettiin vaikuttavan DAP:n ja läpivalaisuaikaan ERCP:ssa. Näiden tekijöiden tiedostaminen voi auttaa tunnistamaan etukäteen ne haastavat ERCP toimenpiteet, jotka voivat aiheuttaa suuria säteilyannoksia potilaille, ja siten mahdollistaa niihin varautumisen.

This thesis deals with the influence of the discharges of the Dukovany Nuclear Power Plant ("Dukovany NPP") and the assessment of impacts on the population and the vicinity of the power plant. The thesis summarizes the issues of tritium 3H discharges into waterways and partially deals with the 14C discharges. Attention is paid especially to the radioisotope of hydrogen 3H, due to its chemical and physical form and its presence in the cooling medium (light water) used by that type of nuclear power reactor. The thesis also contains a description of the current state of the Dukovany NPP, especially the existing discharges of the radioactive substances to the surroundings of the nuclear power plant, both to the air and into the waterway. Also was discussed the issue of the new planned blocks of the Dukovany NPP and impacts of the projected discharges on the population during the simultaneous operation of the existing blocks and the planned blocks, again in relation to the 3H discharged into the waterway. The application ESTE AI was used for the determination of individual groups of inhabitants who are most exposed to the radioactive discharges (also called representative person). Based on the current discharges of the Dukovany NPP and the planned blocks discharges were determined the annual effective doses for a representative person. The doses were compared with the legislation on the conditions for the peaceful use of nuclear energy requirements and then with the water management legislation. In order to avoid exceeding these limits were set up recommendations how to dispose of radioactive substances optimally. The thesis answer to the research question: What impacts on the population will have discharges of the Dukovany NPP after the construction of a new nuclear source, especially in relation to the discharges of the 3H into the waterway and which measures will must be applied on the optimization of the inhabitants doses.

Coordenação de Aperfeiçoamento de Pessoal de Nível Superior - CAPES / The Uraniferous Province of Lagoa Real, in the region of Caetité, located in midwest Bahia State, is considered the most important uraniferous reserve of Brazil. Because it is a uranium mining region, it is important to be evaluated and monitored in order to obtain information on the chemical composition and concentration of radionuclides in water and soil. In this study we determined the specific activity of some radionuclides in soil and water samples collected in February 2014, when high rainfall in the region. The concentration of the activities of radionuclides 226,228Ra and 234,238U in water samples and radionuclides 226Ra, 232Th and 40K in soil samples were found by different techniques of nuclear spectrometry. The water samples showed higher specific activity (134 + 4) mBq / L for 226Ra and (208 + 9) mBq / L for 228Ra. Concerning the isotopes of uranium, the highest activity in the water was (172 + 10) mBq / L for 238U and (447 + 20) mBq / L for 234U. In the soil samples was noted that especially the 40K was most active. The highest value obtained for this radioactive nuclide was (155 + 11) .10 Bq / kg. In samples sand beaches of Rio de Janeiro and Aracaju, used as a reference, the highest activity was the 232Th with (36.4 + 6.1) Bq / kg, and for the 40K all showed a specific activity of < 50 Bq / kg. The soil samples represented very low specific activity for radionuclides investigated, compared to the values established in the Brazilian criteria for exclusion, exemption and waiver as radiation protection requirement. The effective doses were calculated from the activity concentrations of radioactive nuclides in water and their dose coefficients. Two samples exceeded the limits recommended by the WHO that is 100 mSv / a, (144.2 mSv / a) and (102.2 mSv / a), but both are not ingested by the population. The most effective dose calculated for water samples ingested by the population was 58.6 mSv / a, value within the recommended limit. From the data obtained, it can be concluded that the samples did not indicate a high concentration as TENORM and that there seems to be contamination of Caetité region due handling ore in the region. The presence of radionuclides in the samples is due to the nature of the soil region and the operation of uranium. / A Província Uranífera de Lagoa Real, na região de Caetité e Lagoa Real, situado no centro sul da Bahia, atualmente é considerada a mais importante reserva uranífera do Brasil. Por se tratar de uma região de exploração do minério de urânio, é importante ser avaliada e monitorada para que se obtenham informações da composição química e concentração de radionuclídeos na água e no solo. Neste trabalho determinou-se a atividade específica de alguns radionuclídeos em amostras de águas e solos coletadas em fevereiro de 2014, época de alto índice pluviométrico na região. A concentração das atividades dos radionuclídeos 226,228Ra e 234,238U em amostras de água e dos radionuclídeos 226Ra, 232Th e 40K em amostras de solos foram encontrados por diferentes técnicas de espectrometria nuclear. A amostra de água com maior atividade específica apresentou (134 + 4) mBq/L para 226Ra e (208 + 9) mBq/L para 228Ra. Tratando-se isótopos de urânio, a maior atividade na água foi de (172 + 10) mBq/L para o 238U e de (447 + 20) mBq/L para 234U. Nas amostras de solo foi notado que especialmente o 40K apresentou maior atividade. O maior valor obtido para este nuclídeo radioativo foi (155 + 11).10 Bq/kg. Em amostras de areia de praias do Rio de Janeiro e de Aracaju, usadas como referência, a maior atividade foi do 232Th com (36,4 + 6,1) Bq/kg, sendo que para o 40K todas apresentaram uma atividade específica de < 50 Bq/kg. As amostras de solos representaram muito baixa atividade específica para os radionuclídeos investigados, comparadas aos valores estabelecidos nos critérios brasileiros de exclusão, isenção e dispensa como requisito de proteção radiológica. As doses efetivas foram calculadas a partir das concentrações de atividade dos nuclídeos radioativos encontrados na água e de seus coeficientes de dose. Duas amostras excederam os limites recomendados pela OMS que é de 100 mSv/a, (144,2 mSv/a) e (102,2 mSv/a), mas ambas não são ingeridas pela população. A maior dose efetiva calculada para amostras de água ingeridas pela população foi 58,6 mSv/a, valor dentro do limite recomendado. A partir dos dados obtidos, pode-se concluir que as amostras não indicaram uma concentração elevada como TENORM e que não parece haver contaminação da região de Caetité devido movimentação de minério na região. A presença de radionuclídeos nas amostras de solo se deve à natureza do solo da região e não à exploração de urânio.

Medidas da radiação gama ambiental foram feitas em algumas regiões da cidade de Ribeirão Preto-SP, de forma a contribuir para o conhecimento acerca dos níveis desse tipo de radiação no estado de São Paulo e no território brasileiro. Escolheu-se determinar as médias anuais de dose efetiva e dose efetiva coletiva, uma vez que estas grandezas levam em conta o risco de possíveis efeitos biológicos associados a exposição à radiação ionizante. Para determinar os valores dessas grandezas, os diversos setores censitários das regiões selecionadas foram mapeados e avaliados individualmente, de acordo com a taxa de dose média absorvida no ar e número de habitantes de cada setor. Utilizou-se um sistema de detecção da radiação gama baseado em cintilador plástico e GPS, que possibilitaram a medida da taxa de dose absorvida no ar a cada segundo, para as coordenadas geográficas selecionadas. Embora este sistema tenha sido desenvolvido para a detecção de fontes artificiais perdidas, ou seja, não tem o objetivo principal de fazer medidas dosimétricas da radiação gama natural, teve seus modos de leitura calibrados e comparados com resultados da literatura (com uma incerteza média de 8,7 %). Dos resultados obtidos, dos mapeamentos realizados nas regiões consideradas, as médias anuais da dose efetiva e dose efetiva coletiva para ambientes ao ar livre foram encontradas com os valores 0,034 ± 0,004 mSv/ano e 25,62 ± 9,25 homem.mSv/ano respectivamente, sendo a primeira cerca da metade da média mundial da dose efetiva recomendada pela UNSCEAR. As médias obtidas são baixas quando comparadas às encontradas em outros estudos sobre dose de radiação gama ao ar livre no estado de São Paulo e em outras regiões do território brasileiro (sendo, de 1,7 até 5,6 vezes menor). / Gamma environmental radiation measurements were done for some urban regions in the city of Ribeirão Preto-SP, in order to contribute with this knowledge on the annual ambiental values of this type of radiation in the São Paulo state and in the Brazilian territory. The quantities chosen were effective dose and effective collective dose, once they take into account the possible biologic damage related to the ionizing radiation energy absorbed. For the assessments of these quantities, selected census sectors were initially mapped out, regarding their average absorbed dose in air and the number of inhabitants living in each one of the sectors. The detector system used is based on an organic plastic scintillator and a GPS, that allows to obtain the absorbed dose rate for each second and their respective geographic coordinates. Even though this system was developed to detect missing artificial gamma sources, in other words, its main function is not for dosimetric measurements, both display modes were calibrated in exposure rate (R/h) and absorbed dose rate (Gy/h) and their readings were compared to results from the literature (with an average uncertainty of 8.7%). From the mapping results of the selected regions, the annual average effective dose and effective collective dose for outdoor environments were obtained, respectively as 0.034 ± 0.004 mSv/year and 25.62 ± 9.25 man.mSv/year. The value for the first average dose is lower (about half) than the worldwide average value published by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), also lower than the values from other regions in the national territory, regarding the gamma dose rate in outdoor environments (from 1.7 up to 5.6 times lower).