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.

Les mesures fines des faibles radioactivités par la spectrométrie gamma nécessitent l’optimisation de la géométrie de détection et la connaissance du schéma de niveaux des raies gamma. Ainsi, on peut augmenter le taux de comptage et par conséquent, réduire l’incertitude statistique des pics spectraux exploités pour le calcul de l’activité des radio-isotopes en rapprochant le plus possible l’échantillon du détecteur. Cependant, l’augmentation du volume de l’échantillon demande une correction de l’auto-absorption des émissions par l’échantillon même, et le rapprochement du détecteur est à l’origine du phénomène de pic-somme. L’utilisation de MCNPX a permis de mettre en évidence les effets séparés de la densité de l’échantillon et le nombre atomique effectif dans l’atténuation des photons d’énergie inférieure à 100 keV. Les facteurs de correction du pic-somme sont obtenus par MCNPX, GESPCOR et ETNA. Ainsi, une base des données pour 244 radionucléides a été établie pour des géométries SG50 et SG500 au contact d’un détecteur. Dans une application à la radioprotection, des échantillons de matériaux de construction ont été analysés par la spectrométrie gamma. L’Uranium-238, le Thorium-232 et le Potassium-40 ont été identifiés et corrigés des effets sus-cités. La dosimétrie de leurs rayonnements gamma a permis d’évaluer les indices de risque, la dose absorbée et la dose efficace annuelle reçues provenant de ces matériaux. Les simulations par MCNPX corroborent le modèle de calcul de la dose absorbée. Il a permis aussi d'étudier la distribution de la dose dans les habitations de différentes dimensions. Les résultats obtenus sont en accord avec les limites règlementaires. / Precisely measuring weakly radioactive samples by gamma-ray spectrometry requires optimizing the detection geometry and knowledge of the gamma-ray decay scheme. One can thus increase the counting rate and reduce the statistical uncertainty of the spectral peaks used to determine radioisotope activities. However, an increased sample volume requires a correction for the self-absorption of y-rays in the sample itself, and approaching a sample to the detector gives rise to coincidence summing. MCNPX simulations permitted finding the separate influence of sample density and effective atomic number of the sample in the attenuation of photons with energies less than 100 keV. Peak-summing corrections were obtained with MCNPX, GESPCOR and ETNA. Thus a data base for 244 radionuclides could be established for SG50 and SG500 geometries in contact with a planar detector. In an application of the results to the health physics domain, construction materials were analyzed. Naturally-occurring Uranium-238, Thorium-232 and Potassium-40 activities were identified and corrected for the above-mentioned effects in order to evaluate the risk indexes, the absorbed dose and the annual effective dose received from different dimensions built of these materials. MCNPX simulations corroborated the model used to calculate the absorbed dose and gave its distribution in an enclosed space. The results obtained are within the recommended norms.

La spectrométrie γ dose en une seule mesure tous les émetteurs γ dans un échantillon. L’auto-absorption des rayonnements γ dans des échantillons se manifeste par des pertes ou des gains d'impulsions. Pour caractériser une nouvelle géométrie de comptage, des améliorations du dispositif existant ont été apportées par des simulations MCNPX. Avec ce nouveau dispositif nous avons pu spécifier les doses absorbées et efficaces annuelles ainsi que les facteurs de conversion de dose des radioisotopes naturels pour des matériaux de construction et des prélèvements de sols. Des simulations ont montré l’influence des seuils de détection des rayonnements γ donc sur les facteurs de conversion de dose et la nécessité d’une mise à jour de ces facteurs. L’analyse par spectrométrie γ in situ du sol fait appel à des efficacités de détection simulées par MCNPX pour une source aux dimensions semi-infinies. Une application a été réalisée autour d’une centrale nucléaire et une autre pour une société. / Γ-ray spectrometry enables determining all γ-ray emitters in a sample with a single measurement. Self-absorption of γ-rays in samples is manifest by a loss or a gain of pulses that results in a poor estimation of the counting efficiency. To characterize a new counting geometry improvements of the existing set-up were made with MCNPX simulations. With the new geometry we could specify absorbed and annual effective doses as well as dose conversion factors for the natural radioisotopes of several building materials and soil samples. Simulations show the influence of detection limits of γ-radiation on dose conversion factors and the need for updating these factors. γ-ray measurements of soil in situ require different counting efficiencies simulated by MCNPX for a semi-infinite source. Two in-situ soil analyses were made, one around a nuclear power and the other for a private company.

<p>U ovoj doktorskoj disertaciji predstavljena je radiolo&scaron;ka i strukturna karakterizacija građevinskih materijala koji se mogu naći u upotrebi u Srbiji. Izvr&scaron;ena je radiolo&scaron;ka karakterizaicija ukupno 348 uzoraka: granita,&nbsp; fosfogipsa,&nbsp; sirovina&nbsp; u&nbsp; keramičkoj&nbsp; industriji,&nbsp; keramičkih pločica,&nbsp; betona,&nbsp; opeke,&nbsp; maltera,&nbsp; siporeksa,&nbsp; crepa&nbsp; i&nbsp; drugih<br />građevinskih materijala op&scaron;te upotrebe.&nbsp; Radiolo&scaron;ka karakterizacija je&nbsp; sprovedena&nbsp; merenjem&nbsp; koncentracija&nbsp; aktivnosti 226 Ra,232 Th&nbsp; i 40 K metodom&nbsp; gama&nbsp; spektrometrije,&nbsp; kao&nbsp; i&nbsp; ekshalacije&nbsp; radona&nbsp; iz selektovanih&nbsp; građevinskih&nbsp; materijala&nbsp; kori&scaron;ćenjem&nbsp; aktivnih&nbsp; uređaja RAD7,&nbsp; RTM&nbsp; 1688-2,&nbsp; AlphaGUard&nbsp; i&nbsp; AlphaE.&nbsp; Kori&scaron;ćenjem&nbsp; Monte Karlo&nbsp; simulacija&nbsp; izvr&scaron;ena&nbsp; je&nbsp; procena&nbsp; jačina&nbsp; apsorbovanih&nbsp; doza<br />gama&nbsp; zračenja,&nbsp; uočena&nbsp; su&nbsp; odstupanja&nbsp; od&nbsp; teorijski&nbsp; procenjenih vrednosti&nbsp; i&nbsp; dati&nbsp; predlozi&nbsp; za&nbsp; korekciju.&nbsp; Izvr&scaron;ena&nbsp; je&nbsp; procena radijacionog&nbsp; rizika&nbsp; od&nbsp; kori&scaron;ćenja&nbsp; analiziranih&nbsp; građevinskih materijala&nbsp; u&nbsp; enterijeru,&nbsp; kao&nbsp; i&nbsp; za&nbsp; profesionalna&nbsp; lica&nbsp; pri&nbsp; radu&nbsp; sa sirovinskim&nbsp; materijalima.&nbsp; Ispitivane&nbsp; su&nbsp; mogućnosti&nbsp; upotrebe fosfogipsa&nbsp; kao&nbsp; NORM&nbsp; materijala&nbsp; u&nbsp; proizvodnji gips-karton&nbsp; ploča&nbsp; i opeke&nbsp; uz procenu radijacionog rizika od upotrebe.&nbsp; Napravljeno je 8 uzoraka&nbsp; opeke&nbsp; sa&nbsp; različitim&nbsp; udelog&nbsp; fosfogipsa&nbsp; i&nbsp; izvr&scaron;ena&nbsp; je<br />radiolo&scaron;ka&nbsp; i&nbsp; strukturna&nbsp; karakterizacija&nbsp; dobijenih&nbsp; materijala. Ispitivane&nbsp; su&nbsp; varijacije&nbsp; koeficijenata&nbsp; emanacije&nbsp; radona&nbsp; iz građevinskih materijala tokom vremena, kao i uticaj efekata curenja i povratne difuzije koji dovode do tih varijacija. Ispitivan je takođe i uticaj strukture materijala u smislu mineralo&scaron;kog i hemijskog satava i&nbsp; poroznosti&nbsp; na&nbsp; vrednosti&nbsp; koeficijenta&nbsp; emanacije&nbsp; radona. Meneralo&scaron;ka&nbsp; karakterizacija&nbsp; uzoraka&nbsp; izvr&scaron;ena&nbsp; je&nbsp; metodom rendgenske&nbsp; strukturne&nbsp; analize&nbsp; (XRD),&nbsp; a&nbsp; hemijska&nbsp; metodom rendgenske&nbsp; fluorescentne&nbsp; analize&nbsp; (XRF).&nbsp; Merenje&nbsp; ukupne&nbsp; efektivne poroznosti izvr&scaron;eno je metodama apsorpcije vode i metodom živine porozimetrije.&nbsp; Na&nbsp; osnovu&nbsp; dobijenih&nbsp; rezultata&nbsp; uspostavljene&nbsp; su značajne&nbsp; korelacije&nbsp; između&nbsp; pojedinih&nbsp; radiolo&scaron;kih&nbsp; i&nbsp; strukturnih parametara za analizirane uzorke građevinskih materijala.</p> / <p>In&nbsp; this&nbsp; doctoral&nbsp; dissertation,&nbsp; the&nbsp; results&nbsp; of&nbsp; the&nbsp; radiological&nbsp; and structural characterization of building materials used in Serbia were presented.&nbsp; Radiological&nbsp; characterization&nbsp; of&nbsp; a&nbsp; total&nbsp; of&nbsp; 348&nbsp; samples was performed, including granite, phosphogypsum, raw&nbsp; materials&nbsp; in the ceramic industry, ceramic tiles, concrete, brick, mortar, siporex, tiles,&nbsp; and&nbsp; other&nbsp; materials&nbsp; frequently&nbsp; used&nbsp; as&nbsp; building&nbsp; materials.Radiological characterization was performed by measuring activity concentrations&nbsp; of 226 Ra,232 Th,&nbsp; and 40 K&nbsp; by&nbsp; gamma&nbsp; spectrometry method, as well&nbsp; as radon exhalation from selected building materials using active devices RAD7, RTM 1688-2, AlphaGuard and AlphaE.Using&nbsp; Monte&nbsp; Carlo&nbsp; simulations,&nbsp; the&nbsp; absorbed&nbsp; gamma&nbsp; dose&nbsp; rates were&nbsp; estimated.&nbsp; Furthermore,&nbsp; the&nbsp; deviations&nbsp; from&nbsp; the&nbsp; theoretically estimated&nbsp; absorbed&nbsp; dose&nbsp; rates&nbsp; were&nbsp; observed,&nbsp; and&nbsp; suggestions&nbsp; for correction were given. An assessment of the radiation risk from the use&nbsp; of&nbsp; analyzed&nbsp; building&nbsp; materials&nbsp; in&nbsp; the&nbsp; interior,&nbsp; as&nbsp; well&nbsp; as&nbsp; for occupational&nbsp; workers&nbsp; working&nbsp; with&nbsp; raw&nbsp; materials&nbsp; was&nbsp; conducted.The possibilities of using phosphogypsum as a NORM material in the production&nbsp; of&nbsp; gypsum&nbsp; plasterboard&nbsp; and&nbsp; bricks&nbsp; were&nbsp; investigated, with&nbsp; an&nbsp; assessment&nbsp; of&nbsp; the&nbsp; radiation&nbsp; risk&nbsp; due&nbsp; to&nbsp; use&nbsp; of&nbsp; phosphogypsum as a component in the building materials. 8 samples of&nbsp; bricks&nbsp; with&nbsp; different&nbsp; proportions&nbsp; of&nbsp; phosphogypsum&nbsp; were&nbsp; made and&nbsp; radiological&nbsp; and&nbsp; structural&nbsp; characterization&nbsp; of&nbsp; the&nbsp; obtained materials was performed. Variations of radon emanation coefficients from building materials over time, as well as the influence of leakage and&nbsp; back&nbsp; diffusion&nbsp; effects&nbsp; leading&nbsp; to&nbsp; these&nbsp; variations,&nbsp; were investigated. The influence of the structure of the material in terms of mineral and chemical composition and porosity on the values of the radon&nbsp; emanation&nbsp; coefficient&nbsp; was&nbsp; also&nbsp; investigated.&nbsp; The mineralogical characterization of the samples was performed by the method&nbsp; of&nbsp; X-ray&nbsp; structural&nbsp; analysis&nbsp; (XRD),&nbsp; and&nbsp; the&nbsp; chemical characterization&nbsp; by&nbsp; the&nbsp; method&nbsp; of&nbsp; X-ray&nbsp; fluorescence&nbsp; analysis (XRF). The measurement of total effective porosity was performed by water absorption methods and mercury porosimetry method. Based on&nbsp; the&nbsp; obtained&nbsp; results,&nbsp; significant&nbsp; correlations&nbsp; were&nbsp; establishedbetween&nbsp; individual&nbsp; radiological&nbsp; and&nbsp; structural&nbsp; parameters&nbsp; for&nbsp; the analyzed samples of construction materials.</p>