Pre-detonation technical nuclear forensics techniques for research reactor spent fuel were developed in a collaborative project with Savannah River National Lab ratory. An inverse analysis method was employed to reconstruct reactor parameters from a spent fuel sample using results from a radiochemical analysis. In the inverse analysis, a reactor physics code is used as a forward model. Verification and validation of different reactor physics codes was performed for usage in the inverse analysis. The verification and validation process consisted of two parts. The first is a variance analysis of Monte Carlo reactor physics burnup simulation results. The codes used in this work are MONTEBURNS and MCNPX/CINDER. Both utilize Monte Carlo transport calculations for reaction rate and flux results. Neither code has a variance analysis that will propagate through depletion steps, so a method to quantify and understand the variance propagation through these depletion calculations was developed. The second verification and validation process consisted of comparing reactor physics code output isotopic compositions to radiochemical analysis results. A sample from an Oak Ridge Research Reactor spent fuel assembly was acquired through a drilling process. This sample was then dissolved in nitric acid and diluted in three different quantities, creating three separate samples. A radiochemical analysis was completed and the results were compared to simulation outputs at different levels ofdetail. After establishing a forward model, an inverse analysis was developed to re-construct the burnup, initial uranium isotopic compositions, and cooling time of a research reactor spent fuel sample. A convergence acceleration technique was used that consisted of an analytical calculation to predict burnup, initial 235U, and 236U enrichments. The analytic calculation results may also be used stand alone or in a database search algorithm. In this work, a reactor physics code is used as a for- ward model with the analytic results as initial conditions in a numerical optimization algorithm. In the numerical analysis, the burnup and initial uranium isotopic com- positions are reconstructed until the iterative spent fuel characteristics converge with the measured data. Upon convergence of the sample’s burnup and initial uranium isotopic composition, the cooling time can be reconstructed. To reconstruct cooling time, the standard decay equation is inverted and solved for time. Two methods were developed. One method uses the converged burnup and initial uranium isotopic compositions along in a reactor depletion simulation. The second method uses an isotopic signature that does not decay out of its mass bin and has a simple production chain. An example would be 137Cs which decays into the stable 137Ba. Similar results are achieved with both methods, but extended shutdown time or time away from power results in over prediction of the cooling time. The over prediction of cooling time and comparison of different burnup reconstruction isotope results are indicator signatures of extended shutdown or time away from power. Due to dynamic operation in time and function, detailed power history reconstruction for research reactors is very challenging. Frequent variations in power, repeated variable shutdown time length, and experimentation history affect the spectrum an individual assembly is burned with such that full reactor parameter reconstruction is difficult. The results from this technical nuclear forensic analysis may be used with law enforcement, intelligence data, macroscopic and microscopic sample characteristics in a process called attribution to suggest or exclude possible sources of origin for a sample.

The goal of this research was to identify and fabricate zeolitic membranes that can separate radioisotope krypton-85 (half-life 10.72 years) and xenon gas released during spent nuclear fuel reprocessing. In spent nuclear fuel reprocessing, fissionable plutonium and uranium are recovered from spent nuclear fuel and recycled. During the process, krypton-85 and xenon are released from the spent nuclear fuel as process off-gas. The off-gas also contains NO, NO2, 129I, 85Kr, 14CO2, tritium (as 3H2O), and air and is usually vented to the atmosphere as waste without removing many of the radioactive components, such as 85Kr. Currently, the US does not reprocess spent nuclear fuel. However, as a member of the International Framework for Nuclear Energy Cooperation (IFNEC, formerly the Global Nuclear Energy Partnership), the United States has partnered with the international nuclear community to develop a “closed” nuclear fuel cycle that efficiently recycles all used nuclear fuel and safely disposes all radioactive waste byproducts. This research supports this initiative through the development of zeolitic membranes that can separate 85Kr from nuclear reprocessing off-gas for capture and long-term storage as nuclear waste. The implementation of an 85Kr/Xe separation step in the nuclear fuel cycle yields two main advantages. The primary advantage is reducing the volume of 85Kr contaminated gas that must be stored as radioactive waste. A secondary advantage is possible revenue generated from the sale of purified Xe. This research proposed to use a zeolitic membrane-based separation because of their molecular sieving properties, resistance to radiation degradation, and lower energy requirements compared to distillation-based separations. Currently, the only commercial process used to separate Kr and Xe is cryogenic distillation. However, cryogenic distillation is very energy intensive because the boiling points of Kr and Xe are -153 °C and -108 °C, respectively. The 85Kr/Xe separation step was envisioned to run as a continuous cross-flow filtration process (at room temperature using a transmembrane pressure of about 1 bar) with a zeolite membrane separating krypton-85 into the filtrate stream and concentrating xenon into the retentate stream. To measure process feasibility, zeolite membranes were synthesized on porous α-alumina support discs and permeation tested in dead-end filtration mode to measure single-gas permeance and selectivity of CO2, CH4, N2, H2, He, Ar, Xe, Kr, and SF6. Since the kinetic diameter of krypton is 3.6 Å and xenon is 3.96 Å, zeolites SAPO-34 (pore size 3.8 Å) and DDR (pore size 3.6 Å) were studied because their pore sizes are between or equal to the kinetic diameters of krypton and xenon; therefore, Kr and Xe could be separated by size-exclusion. Also, zeolite MFI (average pore size 5.5 Å) permeance and selectivity were evaluated to produce a baseline for comparison, and amorphous carbon membranes (pore size < 5 Å) were evaluated for Kr/Xe separation as well. After permeation testing, MFI, DDR, and amorphous carbon membranes did not separate Kr and Xe with high selectivity and high Kr permeance. However, SAPO-34 zeolite membranes were able to separate Kr and Xe with an average Kr/Xe ideal selectivity of 11.8 and an average Kr permeance of 19.4 GPU at ambient temperature and a 1 atm feed pressure. Also, an analysis of the SAPO-34 membrane defect permeance determined that the average Kr/Xe selectivity decreased by 53% at room temperature due to unselective defect permeance by Knudsen diffusion. However, sealing the membrane defects with polydimethylsiloxane increased Kr/Xe selectivity by 32.8% to 16.2 and retained a high Kr membrane permeance of 10.2 GPU at ambient temperature. Overall, this research has shown that high quality SAPO-34 membranes can be consistently fabricated to achieve a Kr/Xe ideal selectivity >10 and Kr permeance >10 GPU at ambient temperature and 1 atm feed pressure. Furthermore, a scale-up analysis based on the experimental results determined that a cross-flow SAPO-34 membrane with a Kr/Xe selectivity of 11.8 and an area of 4.2 m2 would recover 99.5% of the Kr from a 1 L/min feed stream containing 0.09% Kr and 0.91% Xe at ambient temperature and 1 atm feed pressure. Also, the membrane would produce a retentate stream containing 99.9% Xe. Based on the SAPO-34 membrane analysis results, further research is warranted to develop SAPO-34 membranes for separating 85Kr and Xe.

The thesis deals with nuclear waste deep repositories in the law. With exception of long- term storage the nuclear waste deep repositories represent the only technical solution currently available to deal with the increasing volume of highly radioactive waste and spent nuclear fuel. The planning and construction of nuclear waste deep repository entails number of problems and challenges, both from technical and legal perspectives. The thesis aims to describe current legislation regarding the management of radioactive waste and spent nuclear fuel within the territory of the Czech Republic with a particular focus on planning and construction of a nuclear waste deep repository. There is step by step described procedure of planning and constructing a nuclear waste deep repository under the current legislation. Within this description the author evaluates the current legislation and identifies its major issues. Subsequently, the author reflects on the cause of these issues and proposes their solutions.

Este estudo analisa os gastos realizados por aluno na faixa etária de 0 a 3 anos em creches mantidas e administradas diretamente pelas secretarias de educação de três municípios paulistas que prestam o atendimento em período integral, nos anos de 2012 e 2013. Teve como objetivo apresentar, discutir e aprofundar uma metodologia de análise do gasto aluno, em um ano, para as creches diretas e para isto desenvolveu-se uma metodologia de cálculo do Gasto Aluno Efetivo (GAE), com nove categorias de gastos, tomadas como referência da metodologia do Custo Aluno Qualidade-inicial (CAQi). A questão que norteou o desenvolvimento da pesquisa foi A partir dos levantamentos dos gastos por aluno, com a metodologia de cálculo aqui apresentada, estes valores se aproximam ou se afastam do CAQi e do FUNDEB para as creches de administração direta das redes públicas de ensino?. O desenvolvimento da pesquisa se deu pela modalidade de um estudo de caso e a coleta de dados se deu diretamente nos setores administrativos das secretarias envolvidas na execução orçamentária das três secretarias de educação por conta da participação do pesquisador ora como gestor do sistema educacional (Suzano), ora como funcionário da secretaria de educação (São Bernardo do Campo) ora como consultor e pesquisador (Araçoiaba da Serra). Os valores obtidos para o gasto aluno por meio desta metodologia de cálculo mostraram que os três municípios investem um montante maior do que o proposto pelo CAQi e o repassado pelo Fundeb para esta faixa etária, e, portanto, se afastaram dos valores de referência, porém ao serem analisadas as categorias de gastos individualmente, verificou-se que em algumas delas os valores encontrados situam-se abaixo dos valores do CAQi, demostrando que a metodologia desenvolvida permite um olhar mais aprofundado sobre a destinação dos recursos educacionais para a consolidação de um padrão de qualidade. Como consequência dos valores encontrados para o GAE para as creches diretas, fez-se uma projeção dos recursos necessários para cada município para a consolidação da meta do Plano Nacional de Educação que preconiza o atendimento de no mínimo 50% das crianças de 0 a 3 anos até o final do decênio, ou seja em 2024. / This study analyzes the expenditures made by students in the age group 0-3 years hosted and managed kindergartens directly by education departments of three counties that provide care full time, in the years 2012 and 2013. The objective was to present, discuss and develop a spending analysis methodology student in a year, for direct creches and this developed into a expenditure calculation methodology Effective Student (GAE), with nine categories of spending taken as cost methodology of reference Student Quality-starter (CAQi). The question that guided the development of the research was \"From the surveys of spending per student, with the calculation methodology presented here, these values toward or away from CAQi and FUNDEB for daycare direct administration of networks public education? \". The development of the research was due to the form of a case study and data collection took place directly in the administrative sectors of the departments involved in the budget execution of the three departments of education because of the participation of the researcher or as the educational system manager (Suzano) either as employee education secretariat (São Bernardo do Campo) or as a consultant and researcher (Araçoiaba da Serra). The values obtained for the student spent by this calculation method showed that the three municipalities invest a greater amount than that proposed by CAQi and transferred by Fundeb for this age group, and thus moved away from the reference values, but to be the spending categories individually analyzed, it was found that in some of the values found are below the CAQi values, demonstrating that this methodology allows for a closer look at the allocation of educational resources for the consolidation of a pattern Of Quality. As a result of the values found for the GAE for direct creches, there was a projection of necessary resources for each municipality for the consolidation of the National Education Plan goal that calls for service at least 50% of children aged 0 to 3 years by the end of the decade, ie in 2024.

Atualmente observa-se um aumento significativo no consumo de cervejas com baixo teor alcoólico e cervejas sem álcool. Existe um crescente interesse por este tipo de produto tanto por parte das indústrias cervejeiras como por parte dos consumidores. Este aumento é principalmente devido a questões de saúde e a razões de segurança no trabalho e nas estradas. Além disso, há países onde o consumo de álcool é proibido por lei. Tendo em vista que o consumidor está em busca de novos produtos com características mais próximas possíveis de uma cerveja convencional, o presente trabalho visa analisar uma nova abordagem para a produção de cerveja lager com baixo teor alcoólico, reutilizando o bagaço de malte, um subproduto da indústria cervejeira, como substituinte de parte do malte. Foram obtidas cervejas com as seguintes proporções de bagaço/malte: 0:100, 25/75, 50/50 e 75/25. Nas cervejas com 50 e 75% de bagaço de malte, observou-se uma redução no tempo de fermentação quando comparadas com a cerveja puro malte. A atenuação real de fermentação das cervejas produzidas também foi menor devido a menor fermentabilidade dos mostos. O teor alcoólico das cervejas obtidas em escala de bancada apresentou valores entre 0,665 e 1,615 % (v/v), o que as caracterizam como cervejas de baixo teor alcoólico A cerveja com 25% de bagaço recebeu as maiores notas na análise sensorial, tendo boa aceitação entre os provadores, e foi escolhida para a produção em escala piloto. O perfil de fermentação da cerveja produzida em escala piloto foi similar ao perfil de fermentação da cerveja produzida em escala de bancada. Também foi realizada uma análise sensorial, comparando a cerveja produzida em escala piloto com duas cervejas comercias. A utilização do bagaço de malte como substituinte do malte na fabricação de cervejas com baixo teor alcoólico é uma estratégia viável, produzindo uma bebida com aceitação sensorial semelhante ao de uma cerveja de baixo teor alcoólico comercial. / Nowadays there has been a significant increase in the consumption of beer with low alcohol content and non-alcoholic beers. There is a growing interest on this type of product by both brewers industries and consumers. This increase is mainly due to health issues and safety reasons at work and on the roads. In addition, there are countries where the consumption of alcohol is prohibited by law. Given that the consumer is looking for new products with characteristics as similar as possible of conventional beer, this study aims to analyze a new approach for the production of lager beer with low alcohol content, by reusing brewer\'s spent grain, a by-product of brewing industry, as a substitute of part of the malt. Beers were obtained with the following proportions of bagasse/malt: 0/100, 25/75, 50/50 and 75/25. In beers with 50 and 75% of bagasse, it was observed a reduction in the fermentation time compared with all-malt beer. The Real Attenuation Fermentation of Beer produced was also lower due to lower fermentability of wort. The beers\' alcohol content obtained in laboratory scale showed values between 0.665 and 1.615% (v/v), which characterize them as low-alcohol beers. Beer with 25% of bagasse received the highest scores in sensory analysis, having a good acceptance among the tasters, therefore it was chosen for the production on a pilot scale. The beer\'s fermentation profile produced on pilot scale was similar to the beer\'s fermentation profile produced in laboratory scale. Sensory analysis was also performed, comparing the beer produced in pilot scale with two commercial beers. The use of brewer\'s spent grain as a substitute in the manufacture of beers with low alcohol content is a viable strategy, producing a beverage with sensory acceptance similar to a commercial low-alcohol beer.

Atualmente observa-se um aumento significativo no consumo de cervejas com baixo teor alcoólico e cervejas sem álcool. Existe um crescente interesse por este tipo de produto tanto por parte das indústrias cervejeiras como por parte dos consumidores. Este aumento é principalmente devido a questões de saúde e a razões de segurança no trabalho e nas estradas. Além disso, há países onde o consumo de álcool é proibido por lei. Tendo em vista que o consumidor está em busca de novos produtos com características mais próximas possíveis de uma cerveja convencional, o presente trabalho visa analisar uma nova abordagem para a produção de cerveja lager com baixo teor alcoólico, reutilizando o bagaço de malte, um subproduto da indústria cervejeira, como substituinte de parte do malte. Foram obtidas cervejas com as seguintes proporções de bagaço/malte: 0:100, 25/75, 50/50 e 75/25. Nas cervejas com 50 e 75% de bagaço de malte, observou-se uma redução no tempo de fermentação quando comparadas com a cerveja puro malte. A atenuação real de fermentação das cervejas produzidas também foi menor devido a menor fermentabilidade dos mostos. O teor alcoólico das cervejas obtidas em escala de bancada apresentou valores entre 0,665 e 1,615 % (v/v), o que as caracterizam como cervejas de baixo teor alcoólico A cerveja com 25% de bagaço recebeu as maiores notas na análise sensorial, tendo boa aceitação entre os provadores, e foi escolhida para a produção em escala piloto. O perfil de fermentação da cerveja produzida em escala piloto foi similar ao perfil de fermentação da cerveja produzida em escala de bancada. Também foi realizada uma análise sensorial, comparando a cerveja produzida em escala piloto com duas cervejas comercias. A utilização do bagaço de malte como substituinte do malte na fabricação de cervejas com baixo teor alcoólico é uma estratégia viável, produzindo uma bebida com aceitação sensorial semelhante ao de uma cerveja de baixo teor alcoólico comercial. / Nowadays there has been a significant increase in the consumption of beer with low alcohol content and non-alcoholic beers. There is a growing interest on this type of product by both brewers industries and consumers. This increase is mainly due to health issues and safety reasons at work and on the roads. In addition, there are countries where the consumption of alcohol is prohibited by law. Given that the consumer is looking for new products with characteristics as similar as possible of conventional beer, this study aims to analyze a new approach for the production of lager beer with low alcohol content, by reusing brewer\'s spent grain, a by-product of brewing industry, as a substitute of part of the malt. Beers were obtained with the following proportions of bagasse/malt: 0/100, 25/75, 50/50 and 75/25. In beers with 50 and 75% of bagasse, it was observed a reduction in the fermentation time compared with all-malt beer. The Real Attenuation Fermentation of Beer produced was also lower due to lower fermentability of wort. The beers\' alcohol content obtained in laboratory scale showed values between 0.665 and 1.615% (v/v), which characterize them as low-alcohol beers. Beer with 25% of bagasse received the highest scores in sensory analysis, having a good acceptance among the tasters, therefore it was chosen for the production on a pilot scale. The beer\'s fermentation profile produced on pilot scale was similar to the beer\'s fermentation profile produced in laboratory scale. Sensory analysis was also performed, comparing the beer produced in pilot scale with two commercial beers. The use of brewer\'s spent grain as a substitute in the manufacture of beers with low alcohol content is a viable strategy, producing a beverage with sensory acceptance similar to a commercial low-alcohol beer.

O reprocessamento do elemento combustível constitui uma das etapas do ciclo do combustível e tem por objetivo separar U 235, U238 e Pu239 dos produtos de fissão contidos no elemento combustível queimado para reutilizá -los na fabricação de novos elementos combustíveis. No Brasil, o desenvolvimento do reprocessamento teve início nos anos 70 com a implantação de uma planta piloto de reprocessamento, no Instituto de Pesquisas Energéticas e Nucleares Comissão Nacional de Energia Nuclear/São Paulo (I PEN-CNEN/SP), dando origem à uma instalação, em escala de laboratório, que operou até o início da década de 90. Parte dos rejeitos radioativos, produzidos principalmente a partir dos laboratórios analíticos está armazenados à espera de tratamento no Labora tório de Gestão de Rejeitos do IPEN-CNEN/SP, e são constituído pela mistura de fases aquosa e orgânica. Por conter compostos orgânicos, esses rejeitos não podem se solidificados diretamente com cimento, necessitando para isso, de tratamento prévio para torná-los compatíveis. Desta forma, o objetivo deste trabalho foi desenvolver uma metodologia de biodegradação dos compostos orgânicos que compõem os rejeitos radioativos líquidos orgânicos (RRLO) para que os mesmos possam ser posteriormente imobilizados em c imento. O trabalho foi dividido em três etapas, a de caracterização dos RRLO, obtenção das comunidades microbianas (da mina de urânio de Poços de Caldas e do estuário de São Sebastião) e realização de ensaios de biodegradação dos RRLO. A partir da caracterização dos rejeitos, a biodegradação do TBP e acetato de etila foram monitoradas. Os resultados mostraram que as comunidades bacterianas selecionadas foram eficientes para a degradação dos rejeitos radioativos líquidos orgânicos. Ao final dos experimentos os níveis biodegradação foram de 66% para o acetato de etila e 70% para o TBP. / The research and development program in reproces sing of low burn-up spent fuel elements began in Brazil in 70s, originating the lab -scale hot cell, known as CELESTE located at Nuclear and Energy Research Institute, IPEN - CNEN/SP. The program was ended at the beginning of 90s, and the laboratory was c losed down. Part of the radioactive waste generated mainly from the analytical laboratories is stored waiting for treatment at the Waste Management Laboratory, and it is constituted by mixture of aqueous and organic phases. The most widely used technique for the treatment of radioactive liquid wastes is the solidification in cement matrix, due to the low processing costs and compatibility with a wide variety of wastes. However, organics are generally incompatible with cement, interfering with the hydration and setting processes, and requiring pre -treatment with special additives to stabilize or destroy them. The objective of this work can be divided in three parts: i) organic compounds characterization in the radioactive liquid waste; ii) the occurrence of b acterial consortia from Poços de Caldas uranium mine soil and São Sebastião estuary sediments that are able to degrade organic compounds and third, the development of a methodology to biodegrade organic compounds from the radioactive liquid waste aiming th e cementation From the characterization analysis, TBP and ethyl acetate were chosen to be degrade d. The results showed that selected bacterial consortia were efficient for the organic liquid wastes degradation. At the end of the experiments the biodegradat ion level were 66% for ethyl acetate and 70% for the TBP.

O reprocessamento do elemento combustível constitui uma das etapas do ciclo do combustível e tem por objetivo separar U 235, U238 e Pu239 dos produtos de fissão contidos no elemento combustível queimado para reutilizá -los na fabricação de novos elementos combustíveis. No Brasil, o desenvolvimento do reprocessamento teve início nos anos 70 com a implantação de uma planta piloto de reprocessamento, no Instituto de Pesquisas Energéticas e Nucleares Comissão Nacional de Energia Nuclear/São Paulo (I PEN-CNEN/SP), dando origem à uma instalação, em escala de laboratório, que operou até o início da década de 90. Parte dos rejeitos radioativos, produzidos principalmente a partir dos laboratórios analíticos está armazenados à espera de tratamento no Labora tório de Gestão de Rejeitos do IPEN-CNEN/SP, e são constituído pela mistura de fases aquosa e orgânica. Por conter compostos orgânicos, esses rejeitos não podem se solidificados diretamente com cimento, necessitando para isso, de tratamento prévio para torná-los compatíveis. Desta forma, o objetivo deste trabalho foi desenvolver uma metodologia de biodegradação dos compostos orgânicos que compõem os rejeitos radioativos líquidos orgânicos (RRLO) para que os mesmos possam ser posteriormente imobilizados em c imento. O trabalho foi dividido em três etapas, a de caracterização dos RRLO, obtenção das comunidades microbianas (da mina de urânio de Poços de Caldas e do estuário de São Sebastião) e realização de ensaios de biodegradação dos RRLO. A partir da caracterização dos rejeitos, a biodegradação do TBP e acetato de etila foram monitoradas. Os resultados mostraram que as comunidades bacterianas selecionadas foram eficientes para a degradação dos rejeitos radioativos líquidos orgânicos. Ao final dos experimentos os níveis biodegradação foram de 66% para o acetato de etila e 70% para o TBP. / The research and development program in reproces sing of low burn-up spent fuel elements began in Brazil in 70s, originating the lab -scale hot cell, known as CELESTE located at Nuclear and Energy Research Institute, IPEN - CNEN/SP. The program was ended at the beginning of 90s, and the laboratory was c losed down. Part of the radioactive waste generated mainly from the analytical laboratories is stored waiting for treatment at the Waste Management Laboratory, and it is constituted by mixture of aqueous and organic phases. The most widely used technique for the treatment of radioactive liquid wastes is the solidification in cement matrix, due to the low processing costs and compatibility with a wide variety of wastes. However, organics are generally incompatible with cement, interfering with the hydration and setting processes, and requiring pre -treatment with special additives to stabilize or destroy them. The objective of this work can be divided in three parts: i) organic compounds characterization in the radioactive liquid waste; ii) the occurrence of b acterial consortia from Poços de Caldas uranium mine soil and São Sebastião estuary sediments that are able to degrade organic compounds and third, the development of a methodology to biodegrade organic compounds from the radioactive liquid waste aiming th e cementation From the characterization analysis, TBP and ethyl acetate were chosen to be degrade d. The results showed that selected bacterial consortia were efficient for the organic liquid wastes degradation. At the end of the experiments the biodegradat ion level were 66% for ethyl acetate and 70% for the TBP.

Made available in DSpace on 2017-07-10T15:14:28Z (GMT). No. of bitstreams: 1 DissertacaoJulianaFrigo.pdf: 6348989 bytes, checksum: ddd89a3908e6b3eb7436498c2e8a3e88 (MD5) Previous issue date: 2014-02-19 / Several aspects related to dwelling, wellness and life quality demand specific constructive solutions. Considering that the building is one of the responsible by the environment damages because of the quantity of waste, it is also responsible by the electricity waste from the substance extraction to its final product. This study shows a comparative among five combinations of locks and coatings, like: ceramic bricks (plastered), concrete block (plastered), cured lightweight (painted), soil cement (plastered) and soil cement brick with exposed complement (painted), with the purpose to identify which solution is more adequate considering the lowest cost and less electricity spent involved in its process. The adopted methodological procedure is an exploratory research with an explicative approach that enabled the knowledge about the adopted technologies to the rural dwellings study. This study enabled the inputs classification and comparative, executions and spending, having as the mainly result the more viable technology to the rural dwelling and deserve more attention and incentive while its use in a major scale is the soil cement brick with exposed complement only with waterproofing paint related to the spending and electricity economy involved in the execution and use process. / Diversos aspectos relacionados à moradia, bem estar e qualidade de vida demandam soluções construtivas especificas. Levando em consideração que a construção civil é uma das responsáveis pelos impactos ambientais devido à geração de grandes volumes de resíduos, é a responsável também pelo desperdício de uma significativa parcela de energia, envolvida desde o processo de extração da matéria prima até o produto final. O presente estudo apresenta um comparativo entre cinco combinações de fechamentos e revestimentos, sendo elas: tijolo cerâmico (rebocado), bloco de concreto (rebocado), concreto leve polimerizado (pintado), tijolo de solo-cimento (rebocado) e tijolo de solo-cimento com acabamento a vista (pintado), visando identificar qual a solução apresenta- se mais adequada se tratando de um menor custo aliado a um menor gasto de energia envolvida em seu processo. Para tanto o procedimento metodológico adotado é de uma pesquisa exploratória de abordagem explicativa que possibilitou o conhecimento sobre as tecnologias adotadas para o estudo em habitações sociais rurais. Este trabalho possibilitou a realização da classificação e comparativo das características dos insumos, execuções e custos, tendo como principal resultado que a tecnologia mais viável para habitações sociais rurais e que merece maior atenção e incentivo enquanto sua utilização em maior escala é a de tijolo de solo-cimento com acabamento a vista apenas com pintura impermeabilizante no aspecto de custos e de economia de energia envolvidos em seu processo de execução e utilização.

Three models have been developed and applied in the performance assessment of a final repository. They are based on accepted theories and experimental results for known and possible mechanisms that may dominate in the oxidative dissolution of spent fuel and the release of nuclides from a canister. Assuming that the canister is breached at an early stage after disposal, the three models describe three sub-systems in the near field of the repository, in which the governing processes and mechanisms are quite different. In the model for the oxidative dissolution of the fuel matrix, a set of kinetic descriptions is provided that describes the oxidative dissolution of the fuel matrix and the release of the embedded nuclides. In particular, the effect of autocatalytic reduction of hexavalent uranium by dissolved H2, using UO2 (s) on the fuel pellets as a catalyst, is taken into account. The simulation results suggest that most of the radiolytic oxidants will be consumed by the oxidation of the fuel matrix, and that much less will be depleted by dissolved ferrous iron. Most of the radiolytically produced hexavalent uranium will be reduced by the autocatalytic reaction with H2 on the fuel surface. It will reprecipitate as UO2 (s) on the fuel surface, and thus very little net oxidation of the fuel will take place. In the reactive transport model, the interactions of multiple processes within a defective canister are described, in which numerous redox reactions take place as multiple species diffuse. The effect of corrosion of the cast iron insert of the canister and the reduction of dissolved hexavalent uranium by ferrous iron sorbed onto iron corrosion products and by dissolved H2 are particularly included. Scoping calculations suggest that corrosion of the iron insert will occur primarily under anaerobic conditions. The escaping oxidants from the fuel rods will migrate toward the iron insert. Much of these oxidants will, however, be consumed by ferrous iron that comes from the corrosion of iron. The nonscavenged hexavalent uranium will be reduced by ferrous iron sorbed onto the iron corrosion products and by dissolved hydrogen. In the transport resistance network model, the transport of reactive actinides in the near field is simulated. The model describes the transport resistance in terms of coupled resistors by a coarse compartmentalisation of the repository, based on the concept that various ligands first come into the canister and then diffuse out to the surroundings in the form of nuclide complexes. The simulation results suggest that carbonate accelerates the oxidative dissolution of the fuel matrix by stabilizing uranyl ions, and that phosphate and silicate tend to limit the dissolution by the formation of insoluble secondary phases. The three models provide powerful tools to evaluate "what if" situations and alternative scenarios involving various interpretations of the repository system. They can be used to predict the rate of release of actinides from the fuel, to test alternative hypotheses and to study the response of the system to various parameters and conditions imposed upon it. / QC 20100521