Pasta de cimento é um material comum em repositórios para rejeitos radioativos, atuando como material estrutural e de imobilização. Sua utilização como material de preenchimento em um repositório tipo poço tubular profundo para fontes seladas, no entanto, requer um maior tempo de vida útil do material. O conhecimento de seu comportamento em longo prazo é necessário para garantir a segurança da instalação em milhares de anos. O presente trabalho avaliou as alterações na pasta de cimento induzidas por fatores de degradação, como ataque de agentes agressivos, alta temperatura e presença de campo de radiação. Corpos de prova (cps) de pasta de cimento foram submetidos a ensaios acelerados de degradação e os efeitos deletérios foram avaliados por meio de ensaios de resistência mecânica, variação dimensional, lixiviação/penetração de íons, DRX, TGA e MEV. Observou-se que a hidratação dos cps foi beneficiada pela imersão (em água destilada ou em solução salina) e alta temperatura, resultando em uma resistência maior. O armazenamento à seco prejudicou a hidratação, mantendo a resistência mais baixa. O tempo de imersão e a irradiação não foram capazes de alterar a mineralogia e a resistência da pasta de cimento. / Cement paste is widely used in repositories for radioactive wastes, acting as structural and immobilization material. However, its use as backfill material in boreholes for sealed sources requires a longer service life of this material. The assessment of the cement paste behavior in long term is needed to improve the confidence that the material will perform as required during the service life of the facility. This research evaluated the changes in cement paste induced by degradation parameters. Portland cement paste specimens (cps) were submitted to accelerated degradation tests and the damage effects was evaluated by mechanical strength, variation of sample mass and volume, leaching/penetration of ions, XRD, TGA and SEM. It was observed that cps hydration was benefited by immersion (in distilled water or salt solution) and high temperatures, resulting in a higher strength. Dry storage, however, influenced the hydration process and maintained strength lower. Time of treatment and irradiation were not able to alter mineralogy and durability of cement paste.

As fontes radioativas seladas em desuso, descartadas como rejeito radioativo, constituem uma parcela dos rejeitos radioativos que merece atenção especial, por sua atividade possuir potencial para causar doses de radiação elevadas, em indivíduos inadvertidamente expostos. Já é significativo o volume desses rejeitos. Manter essas fontes armazenadas em depósitos provisórios, indefinidamente, seria transferir o problema às futuras gerações. O presente estudo propõe o uso de indicadores de segurança complementares à dose e risco para o desenvolvimento de uma metodologia de avaliação da segurança de depósitos finais destinados à deposição de fontes radioativas seladas que demonstre que o isolamento será suficientemente seguro pelo tempo necessário para obter a licença da instalação, com custo acessível aos países em desenvolvimento. / Disused sealed radioactive sources are a kind of radioactive waste that deserves especial attention because the radioactivity present in a relevant fraction of the number of sources is high enough to cause severe effects in accidentally exposed individuals. The present inventory of disused sources is of the order of tens of thousands. Keep these sources indefinitely under interim storage is bequeath the problem of final disposal to the future generations. The present study proposes the use of Safety Indicators as a contribution to the development of methodologies for the assessment of safety in a deep borehole repository for sealed sources. These methodologies are required to demonstrate the long-term safety at a cost affordable to developing countries.

O carvão ativado é um tipo comum de rejeito radioativo que contém elevada concentração de produtos de ativação e fissão. O gerenciamento deste rejeito inclui a sua caracterização, visando à determinação e quantificação dos radionuclídeos específicos, incluindo aqueles conhecidos como Radionuclídeos de Difícil Medição (RDM). A análise dos RDMs geralmente envolve análises radioquímicas complexas para purificação e separação dos radionuclídeos, as quais são caras e demandam muito tempo. O objetivo deste trabalho foi definir uma metodologia de análise sequencial de isótopos de urânio, netúnio, plutônio, amerício e cúrio, presentes em um tipo de rejeito radioativo, avaliando-se rendimento químico, tempo de análise, quantidade de rejeito secundário gerado e custo. Foram comparadas e validadas três metodologias que empregam a troca iônica (TI + EC), extração cromatográfica (EC) e extração com polímeros (ECP). O rejeito estudado foi o carvão ativado, proveniente do sistema de purificação de água do circuito primário de refrigeração do reator IEA-R1. As amostras de carvão foram dissolvidas por digestão ácida, seguida de purificação e separação dos isótopos com resinas de troca iônica, extração cromatográfica e extração com polímeros. Os isótopos foram analisados em um espectrômetro alfa, equipado com detectores de barreira de superfície. O rendimento químico de todos os elementos foi satisfatório para os métodos TI + EC e EC. Para o método ECP, apenas o rendimento químico do U foi comparável aos outros métodos. As análises estatísticas dos resultados bem como a análise de custo e volume de rejeito secundário gerado demonstraram que o método EC é o mais adequado para a identificação e quantificação dos isótopos estudados em carvão ativado. / Activated charcoal is a common type of radioactive waste that contains high concentrations of fission and activation products. The management of this waste includes its characterization aiming the determination and quantification of the specific radionuclides including those known as Difficult-to-Measure Radionuclides (RDM). The analysis of the RDM\'s generally involves complex radiochemical analysis for purification and separation of the radionuclides, which are expensive and time-consuming. The objective of this work was to define a methodology for sequential analysis of the isotopes of uranium, neptunium, plutonium, americium and curium present in a type of radioactive waste, evaluating chemical yield, analysis of time spent, amount of secondary waste generated and cost. Three methodologies were compared and validated that employ ion exchange (TI + EC), extraction chromatography (EC) and extraction with polymers (ECP). The waste chosen was the activated charcoal from the purification system of primary circuit water cooling the reactor IEA-R1. The charcoal samples were dissolved by acid digestion followed by purification and separation of isotopes with ion exchange resins, extraction and chromatographic extraction polymers. Isotopes were analyzed on an alpha spectrometer, equipped with surface barrier detectors. The chemical yields were satisfactory for the methods TI + EC and EC. ECP method was comparable with those methods only for uranium. Statistical analysis as well the analysis of time spent, amount of secondary waste generated and cost revealed that EC method is the most effective for identifying and quantifying U, Np, Pu, Am and Cm present in charcoal.

Um aspecto fundamental da aceitação pública da energia nuclear é a crença de que os rejeitos radioativos podem ser gerenciados de maneira segura, no intuito de proteger os seres humanos dos possíveis efeitos prejudiciais, tanto nas gerações atuais como nas futuras. Neste sentido, é essencial compreender como as pessoas percebem o risco associado com rejeitos radioativos e quais são os principais fatores que conduzem suas atitudes em relação à eliminação destes. Uma das maneiras para alcançar esse entendimento é através de pesquisas de opinião. Neste estudo, foi proposto um questionário focado na questão da aceitabilidade da energia nuclear e sua associação com a gestão de rejeitos radioativos, cobrindo os seguintes aspectos: atitudes em relação à energia nuclear e aos rejeitos radioativos, credibilidade das instituições e setores responsáveis pela segurança nuclear, identificação dos benefícios percebidos; percepção do risco de determinadas tecnologias e atividades, percepção do risco real, compreensão das reações emocionais e princípio da precaução. Resultados obtidos a partir de uma aplicação piloto do questionário são apresentados e discutidos neste trabalho. / One of the key features for public acceptance of nuclear energy is the belief that radioactive waste can be managed safely, in order to protect human beings from its possible harmful effects in present and future generations. In this sense, it is essential to understand how people perceive the risk associated with radioactive waste and which the main factors driving their attitudes toward its disposal are. One of the ways to achieve this understanding is through opinion polls. In this study, a questionnaire focused on the nuclear energy aceitability issue and its association with radioactive waste management was proposed, covering the following aspects: attitudes towards radioactive waste and nuclear power, credibility on institutions and sectors responsible by the nuclear safety, identification of perceived benefits, risk perception of specific technologies and activities, perception of real risk, emotional reaction comprehension and precautionary principle. Results obtained from a pilot questionnaire application are presented and discussed in this paper.

As fontes radioativas seladas em desuso, descartadas como rejeito radioativo, constituem uma parcela dos rejeitos radioativos que merece atenção especial, por sua atividade possuir potencial para causar doses de radiação elevadas, em indivíduos inadvertidamente expostos. Já é significativo o volume desses rejeitos. Manter essas fontes armazenadas em depósitos provisórios, indefinidamente, seria transferir o problema às futuras gerações. O presente estudo propõe o uso de indicadores de segurança complementares à dose e risco para o desenvolvimento de uma metodologia de avaliação da segurança de depósitos finais destinados à deposição de fontes radioativas seladas que demonstre que o isolamento será suficientemente seguro pelo tempo necessário para obter a licença da instalação, com custo acessível aos países em desenvolvimento. / Disused sealed radioactive sources are a kind of radioactive waste that deserves especial attention because the radioactivity present in a relevant fraction of the number of sources is high enough to cause severe effects in accidentally exposed individuals. The present inventory of disused sources is of the order of tens of thousands. Keep these sources indefinitely under interim storage is bequeath the problem of final disposal to the future generations. The present study proposes the use of Safety Indicators as a contribution to the development of methodologies for the assessment of safety in a deep borehole repository for sealed sources. These methodologies are required to demonstrate the long-term safety at a cost affordable to developing countries.

No description available.

<p> </p><p>Radioactive waste has been accumulated at CERN as unavoidable consequence of the use of particle accelerators. The elimination of this waste towards the final repositories in France and Switzerland requires the determination of the radionuclide inventory. In order to calculate the residual induced radioactivity in the waste, it is necessary to determine the spectra of secondary particles which are responsible for the material activation. In complex irradiation environments like in an accelerator tunnel it is expected that the secondary particle spectra vary with the characteristics of the machine components in a given section of tunnel. In order to obtain the production rates of the radionuclides of interest the spectra of secondary particles are to be folded with the appropriate cross sections. Though technically feasible, it would be impractical to calculate the particle spectra in every area of any machine and for all possible beam loss mechanisms. Moreover, a fraction of the waste has unknown radiological history, which makes it impossible to associate an item of waste to a precise area of the machine. Therefore it is useful to try to calculate “representative spectra”, which shall apply to a relatively large part of the accelerator complex at CERN. This thesis is dedicated to the calculation of representative spectra in the arcs of the 450 GeV proton synchrotron, SPS, at CERN. The calculations have been performed using the Monte Carlo code FLUKA. Extensive simulations have been done to assess the dependence of proton, neutron and pion spectra on beam energy, size of the nearby machine component and position with respect to the beam-loss point. The results obtained suggest that it is possible to define one single set of representative spectra for all the arcs of the SPS accelerator, with a minor error associated with the use of these. </p><p> </p>

Levels of ⁶⁵Zn in water, sediments, plants, and animals in Alder Slough, a small ecosystem in the Columbia River Estuary, were determined periodically during a one year period. Concentrations of total Zn in organisms were also measured to permit computation of specific activities (μCi⁶⁵Zn/g total Zn). Temporal fluctuations in the activities of ⁶⁵Zn and the concentrations of total Zn occurred in all components of the ecosystem. Activities of ⁶⁵Zn and concentrations of total Zn varied among individual fish from the study area. Pooled estimates of population standard deviations of these values in all samples of two fish species taken during the year amounted to about 20% of their grand means. Usually, individuals with high ⁶⁵Zn activities also proved to have high total Zn concentrations, hence specific activities were less variable than either ⁶⁵Zn or total Zn. The nuclear reactors at Hanford, Washington, the source of most of the ⁶⁵Zn in the Columbia River, were shut down for approximately 45 days during this study. This event presented the opportunity to investigate the response of various components of the ecosystem to reduced ⁶⁵Zn input. The rates of ⁶⁵Zn specific activity decline in several organisms were measured following reactor shutdown. The time required for specific activity of an organism to be reduced by one-half under the conditions prevailing is termed "ecological half-life". The "ecological half-life" differs from the biological half-life of an organism because: 1. it is defined in terms of specific activity 2. it reflects the continued addition of radioactivity to the organism from its food web and water. "Ecological half-lives" vary with the trophic levels of the organisms and with changes in prevailing ecological conditions. / Graduation date: 1968

Shallow land burial in vadose zone sediment at the Hanford Site in Washington is being considered for the disposal of Category 3 low-level waste. A series of column experiments were conducted to evaluate and model the performance of the soil surrounding the trench encasement material for iodine-129 and technetium-99 by evaluating the mobility of these nuclides through the surrounding Trench 8 soil. These experiments were designed to determine effective diffusion coefficients for ¹²⁷I and ⁹⁹Tc through the following system: from contaminated soil into uncontaminated soil. The tests were performed at two different soil moisture contents to evaluate the effects of soil moisture content on diffusion. This thesis describes the experimental methods and presents the diffusion results for this media type. It was found that as the moisture content increased the diffusion increased by an order of magnitude (iodine 4% and 7% moisture content soil effective diffusion coefficients were 8.90E-08 and 1.84E-07 cm²/s respectively, and technetium 4% and 7% moisture content soil diffusion coefficients were 7.61E-08 and 1.45E-07 cm²/s respectively). These results, in combination with other diffusion systems results, will allow the development of release models and contaminant migration models that can be used to estimate the long-term fate of dose-controlling radionuclides that are or will be buried in solid waste burial trenches. / Graduation date: 2004

Chitosan is a biopolymer resulting from the deacetylation of chitin, the second most abundant biopolymer in nature. Chitosan has been successfully used in systems to remove metal ions and other pollutants from wastewater. Chitosan has shown promise as a sorbent for radionuclides in some aqueous waste streams. The sorption of these radionuclides by chitosan is studied to determine if chitosan could be used as a sorbent for aqueous waste streams containing these metals. The effect of various experimental conditions including sorbent particle size, agitation rate, hydration, temperature, pH, metal concentration and sorbent concentration are examined in this study. Results showed that sorption depends on the availability of access sites, controlled by the specific surface area of the sorbent. Sorption was observed to decrease with increasing temperature. The sorption isotherms and kinetics for Co(II), Eu(III) and U(VI) sorption onto chitosan were determined experimentally by batch sorption. Isotherms were fitted using the Langmuir and Freundlich models. Kinetics were modeled using the pseudo- first order, pseudo-second order, Elovich, and intraparticle diffusion models in order to determine possible rate-limiting steps. Most data were well described by the pseudo- second order and Elovich models. Multi-linearity was observed in the intraparticle diffusion model. The sorption capacity of the metals on chitosan was found to follow the order Co < Eu < U. / Graduation date: 2013