The use of positron-emitting tracers has been extended beyond tomographic facilities in the last few years, giving rise to a general positron-emitting tracing technique. The methodological part of the present thesis involved the evaluation of the performance of storage phosphor (SP) plates, with tracers labeled with high-energy, short-lived, positron-emitting radionuclides, using homogenized tissue specimens and autoradiography with frozen brain sections. The SP plates showed superior sensitivity and a linear response over a wide radioactivity range. Autoradioradiography provided reliable results due to (a) adequate sensitivity for low radioactivity concentration, b) an excellent linear range, and (c) satisfactory resolution. Though equilibration time of receptor-ligand interaction was dependent upon section thickness, quantification was possib with thinner sections. An initial finding using frozen section autoradiography of rat brain and spinal cord showed preferential binding of [11C]4-NMPB, a muscarinic acetylcholine (mACh) receptor antagonist, to the M4 subtype of mACh receptors. Further work to ascertain this specificity, by use of binding studies on cell membranes from CHO-K1 cells expressing individual subtypes of human mACh receptors, suggested lack of subtype selectivity. With respect to the possible cliinical use in glutamatergic neuropathology, [11C]cyano-dizocilpine, as a potential PET tracer for the N-methyl-D-aspartate (NMDA) subtype of glutamate receptors, was studied. The in vivo visualization of specific binding could not be achieved, though in vitro binding demonstrated good specificity and preferential binding to the activated for of the NMDA receptors. The use of the glucose analogue [18F]fluorodeoxyglucose (FDG) to study glucose utilization was evaluated in experimental traumatic brain injury (TBI). A trauma-induced increased uptake of FDG was seen, whereas the uptake of [1-14C]glucose remained unchanged. This discrepancy might be due to the increased postraumatic affinity of FDG for the endothelial glucose transporter proteins and/or to the hexokinase enzyme. [11C]Cyano-dizocilpine, [11C]4-NMPB, and [11C]flumazenil were utilized in autoradiography to evaluate changes in NMDA, mACh, and GABAA receptors, espectively, in experimental TBI. Observations showed a global decrease in the binding potential BP) of (i) [11C]cyano-dizocilpine acutely and 12 hrs after TBI, and (ii) of [11C]4-NMPB at 12 hrs after TBI, and (iii) a decrease in the BP of [11C]flumazenil in the cortex and hippocampus ipsilateral to the site of injury. The demonstrated changes in receptor binding after TBI are indicative of a widely dissipated effect of TBI on the particular neurotransmitter receptor systems as compared with what would be expected from FDG studies after TBI, i.e., a local disturbed neurotransmission.

Radionuclides, 129I and 239,240Pu, are major products or by-products of nuclear fission and among the top risk drivers for waste disposal at the Savannah River Sites (SRS) and Rocky Flats Environmental Technology Sites (RFETS), respectively, due to their perceived mobility in the environment, excessive inventory, toxicity, and long half-life. The objective of this study is to investigate the role of natural organic matter in retarding or facilitating the migration of 129I and 239,240Pu in the Department of Energy (DOE) sites. Measurements of 127I and 129I in humic acids (HAs) and fulvic acids (FAs) obtained by five successive alkaline, two glycerol and one citric acid-alkaline extractions, demonstrated that these extractable humic substances (HS) together account for 54-56 percent and 46 percent of the total 127I and 129I in the soil, respectively. The variations among 127I and 129I concentrations, isotopic ratios (129I/127I), chemical properties of all these humic substances indicated iodine was bound to a small-size aromatic subunit (~10 kDa), while the large-size subunit (~90 kDa), which likely linked the small-size unit through some weak chemical forces, determined the relative mobility of iodine bound to organic matter. Soil resuspension experiments simulating surface runoff or stormflow and erosion events were conducted with soils collected from SRS. Results showed that 72-77 percent of the newly-introduced I- or IO3- were irreversibly sequestered into the organic-rich soil, while the rest was transformed into colloidal and dissolved organo-iodine by the soil. The resulting iodine remobilization contradicts the conventional view that considers only I- or IO3- as the mobile forms. Quantitative structure analysis by 13C DPMAS NMR and solution state 1H NMR on these humic substances indicate that iodine is closely related to the aromatic regions containing esterified products of phenolic and fomic acid or other aliphatic carboxylic acids, amide functionalities, quinone-like structure activated by electron-donating groups (e.g., NH2) or hemicelluloses-lignin-like complex with phenyl-glycosidic linkage. The micro-molecular environment, such as the hydrophobic aliphatic periphery hindering the active aromatic cores and the hydrophilic polysaccharides favoring its accessibility towards hydrophilic iodine species, play another key role in the interactions between iodine and SOM. NMR spectra of the colloidal organic Pu carrier which can potentially be released from the soil during the surface runoff or stormflow showed Pu was transported, at sub-pM concentrations, by a cutin-derived soil degradation products containing siderophore-like moieties and virtually all mobile Pu.

The study is devoted to problems of exposure caused by radionuclides in construction materials. Results received by gamma measurements and calculations (dose modeling) are used. Construction materials produced and/or used in Lithuania were investigated. The results of measurements (concentrations of natural radionuclides and activity indexes) are given for different types of construction materials. On the basis of these results and peculiarities of use of construction materials they have been classified according to their radiological significance. It helps to determine possible amounts of construction materials to be investigated and priorities of investigations. Relationship between activity indexes of different construction materials and dose rates in premises constructed of these construction materials has been determined. It might be used for increase of precision of personal dosimetric measurements performed in premises constructed of different materials. Possible relationship between absorbed dose rate indoors and concentration of indoor radon is discussed. Results of measurements of concentrations of natural radionuclides in archeological samples of construction materials are also presented and discussed. Dose modeling has been performed with the help of ALARA planning tool Visiplan 3D. Distributions of absorbed dose rate in standard living premises have been determined, relationship between dose rate and different parameters of constructions, such as thickness... [to full text]

The study is devoted to problems of exposure caused by radionuclides in construction materials. Results received by gamma measurements and calculations (dose modeling) are used. Construction materials produced and/or used in Lithuania were investigated. The results of measurements (concentrations of natural radionuclides and activity indexes) are given for different types of construction materials. On the basis of these results and peculiarities of use of construction materials they have been classified according to their radiological significance. It helps to determine possible amounts of construction materials to be investigated and priorities of investigations. Relationship between activity indexes of different construction materials and dose rates in premises constructed of these construction materials has been determined. It might be used for increase of precision of personal dosimetric measurements performed in premises constructed of different materials. Possible relationship between absorbed dose rate indoors and concentration of indoor radon is discussed. Results of measurements of concentrations of natural radionuclides in archeological samples of construction materials are also presented and discussed. Dose modeling has been performed with the help of ALARA planning tool Visiplan 3D. Distributions of absorbed dose rate in standard living premises have been determined, relationship between dose rate and different parameters of constructions, such as thickness... [to full text]

The importance of possible consequences of radiation, possible health hazard of people and the radionuclide contamination of the environment requires securing radiation protection from the very start of any operation, where radioactive substances are being handled with. One of these fields is the uranium industry in which DIAMO, state enterprise, takes an important position, dealing with the extraction and treatment of uranium, effacing the impacts of mining, remediation and disposal. Findings in the field of uranium industry are primarily won in form of research of professional information sources. In the theoretical part of the work, historical data about the founding and development of the organisation DIAMO, state enterprise, about carried out operations and the affect on the environment are being listed. Furthermore, information concerning radiation protection, its history, principles and measures are being elaborated. On the basis of carried out analysis and gauging results the level of secured radiation protection in DIAMO, state enterprise, is being assessed. Comparing the analysis of currently valid legal regulations to the analysis of safety documentation worked out in DIAMO, state enterprise, the fulfilment of requirements of legal standards is being assessed. In areas affected with uranium industry (Příbram, Stráž pod Ralskem, Mydlovary) gauging the dose equivalent power consupmtion of gama radiation has been carried out. In selected sites water and soil samples have been taken to assess the concentration of radionuclides. The results of the research are being compared to the measuremet results from other sources. In conclusion it is possible to state that the results in the carried out research are comparable to the results of similar researches carried out in other countries.

The goal of the thesis was to analyse the space arrangement of the gamma - spektrometry laboratory at the RC SÚJB České Budějovice in order to design an optimal regime in a radiological emergency.

At the nuclear power plant accident, the radionuclides with very short half-life come to enviroment, they decay the period from several second to several months. On the other sides come to enviroment radionuclides with long half-life. Their radionuclides occur in surrounding of the power plant for hundreds of years before they decay totally. Immediately after a nuclear power plant accident, radioiodine represents the most severe health hazard for population. Because it is a radionuclide with short half-life, it causes the danger during first months after the accident. Its health hazard lies in the fact, that it gets to food chains and irradiates a man, who consumed contaminated water and food. Radiocaesium and radiostrontiom are the next important radionuclides. They have long half-lifes, it means that will decay after hundred years after the accident and they endanger population a long time after the accident yet.

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.

Os nanotubos naturais da paligorsquita, por apresentarem propriedades físicas e químicas específicas, têm potencial uso como nano sorventes e matrizes para imobilização, retenção, e solidificação de radionuclídeos presentes em efluentes nucleares. No processo de desenvolvimento de materiais com propriedades de sorção visando a incorporação e imobilização de radionuclídeos, as etapas mais importantes são a geração de sítios ativos simultaneamente com o aumento da área superficial específica e tratamento térmico adequado para conduzir ao colapso estrutural. Neste estudo foram avaliados parâmetros e condições determinantes no processo de ativação dos nanotubos naturais da paligorsquita visando a sorção de radionuclídeos de interesse na estrutura dos nanotubos e a avaliação posterior dos parâmetros que afeitam ao colapso estrutural por tratamento térmico. Por este estudo constatou-se que a otimização do processo de ativação ácida é fundamental para o aumento da capacidade de sorção de níquel usando estruturas de nanotubos naturais ativados. A condição otimizada de ativação superficial, mantendo a integridade estrutural foi removido cerca de 33,3% dos cátions de magnésio, equivalente a 6,30·10-4 mol·g-1 de magnésio em massa, aumentando a área superficial específica em 42,8%. Este aspecto permitiu a incorporação de mesma concentração molar de níquel presente nos rejeitos radioativos líquidos em um tempo de processo de 80min. / Natural palygorskite nanotubes show suitable physical and chemical properties and characteristics to be use as potential nanosorbent and immobilization matrix for the concentration and solidification of radionuclides present in nuclear wastes. In the development process of materials with sorption properties for the incorporation and subsequent immobilization of radionuclides, the most important steps are related with the generation of active sites simultaneously to the increase of the specific surface area and suitable heat treatment to producing the structural folding. This study evaluated the determining parameters and conditions for the activation process of the natural palygorskite nanotubes aiming at the sorption of radionuclides in the nanotubes structure and subsequent evaluation of the parameters involve in the structural folding by heat treatments. The optimized results about the maximum sorption capacity of nickel in activated natural nanotubes show that these structures are apt and suitable for incorporation of radionuclides similar to nickel. By this study is verified that the optimization of the acid activation process is fundamental to improve the sorptions capacities for specifics radionuclides by activated natural nanotubes. Acid activation condition optimized maintaining structural integrity was able to remove around 33.3 wt.% of magnesium cations, equivalent to 6.30·10-4 g·mol-1, increasing in 42.8% the specific surface area and incorporating the same molar concentration of nickel present in the liquid radioactive waste at 80 min.

Le retraitement des déchets radioactifs est un problème crucial de nos jours. Ce travail est dédié au développement de nouveaux systèmes d'extraction des radionucléides sur la base de solvants "verts", les liquides ioniques (LI). Dans ce but, des LI ont été fonctionnalisés avec des motifs variés : oxyde de phosphine, carbamoyl oxyde de phosphine et fragments malonamides. De même, les plateformes calix[4]arènes ont été utilisées pour la synthèse de LI fonctionnalisés (LIF) et de leurs précurseurs. Des LIF de deux types (cationiques et anioniques) ont été obtenus.Les LIF synthétisés ont été testés pour l'extraction liquide/liquide de radionucléides. Il a été montré que l'extraction est bien due aux motifs extractants. Toutefois, la charge de l'ion modifié influence l'extraction.Différentes expériences d'extraction et une modélisation mathématique ont été effectuées pour déterminer les mécanismes d'extraction. Ces études ont montré que chacun des systèmes d'extraction est caractérisé par un ensemble d'équilibres d'extraction différent, basés essentiellement sur l'échange cationique. / Radioactive waste treatment is a crucial problem nowedays. This work was dedicated to the development of the new extracting systems for radionuclides on the basis of "green" solvents Ionic Liquids {Ils). For this purpose Ils were functionalized with various extracting patterns: phosphine oxide, carbamoyl phosphine oxide groups and malonamide fragment. Also the calix[4]arene platforms were used for the synthesis of functionalized ionic liquids (Fils) and their precursors. The Fils of both types cationic and anionic have been obtained. The synthesized Fils were tested for the liquid-liquid extraction of radionuclides. lt was found that extraction well occurs due to the extracting patterns, however a charge of a modified ion influences extraction.The various extracting experiments and mathematical modelling have been performed to determine the mechanisms of extraction. These studies showed that each extracting system is characterized by a different set of extracting equilibria, based mostly on cationic exchange.