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LEITE, ELIANA R. "Indicadores de segurança para um d´pósito final de fontes radioativas seladas." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10142.
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Franzén, Jonas, and Jim Kautto. "Kampanjmottagande : Hur tas Regionförbundet i Kalmar läns kampanj om slutförvar av använt kränbränsle emot av målgruppen?" Thesis, University of Kalmar, School of Communication and Design, 2009. http://urn.kb.se/resolve?urn=urn:nbn:se:hik:diva-1928.
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<p>Authors: Jonas Franzén and Jim Kautto</p><p>Title: Information campaign analysis of the Region Council of Kalmar Counties public information campaign about final storage of radioactive waste.</p><p>Level: BA Thesis in Media and Communication Studies.</p><p>Key words: Campaign, Campaign analysis, final storage of radioactive waste, Region Council.</p><p>Language: Swedish</p><p>Content: The Regional Council of Kalmar County launched a campaign about final storage of radioactive waste in the spring of 2009. This study analyzes how that campaign was received by the target group.</p><p>Theory: Following theories have been used in the study; theories of communication, planning of communication, public campaigns and receptions studies.</p><p>Method: Methods used in this study is observing people passing the exhibition, asking questions to people passing the exhibition and two focus groups. We also asked questions to people riding the bus where the commercial was shown. Finally we got background information from two interviews with the creators of the campaign.</p><p>Results: The campaign was launched based on a political decision. Despite that the decision was vague and that the Region Council was lacking a clear objective and measureable goals, the campaign still came out as a success. Since the objective with the campaign was to broaden the dialogue regarding final storage of radioactive waste, and make the public more informed about what could happen in Oskarshamn if the final storage comes there, the campaign succeeded in waken up some interest from the public opinion. The studies could not determine whether the campaign decreased the public's worries about the final storage of radioactive waste or not.</p><p>Number of pages: 49 + appendix</p><p>Program: Program for International Communication</p><p>Location: University of Kalmar</p><p>Institution: Institution of Communication and Design</p><p>Period: Spring of 2009</p><p>Tutor: Sara Hamqvist</p><p>Examiner: Britt-Marie Ringfjord</p>
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Silva, Fábio. "Sistema de gestão integrada de dados para repositórios de rejeitos radioativos (SGI3R)." CNEN - Centro de Desenvolvimento da Tecnologia Nuclear, Belo Horizonte, 2010. http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=134.
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Nenhuma<br>A implantação de um repositório para rejeitos radioativos é um projeto multidisciplinar que
demanda além de especialistas de diferentes áreas do conhecimento, a interação com
instituições públicas e privadas, dados e informações relacionadas com rejeitos radioativos,
geologia, tecnologia etc. Todas as atividades devem estar em conformidade com as normas,
requisitos e procedimentos, incluindo a legislação nacional e internacional. A manutenção dos
registros de inventário dos rejeitos é um requisito importante regulamentar e deverá estar
disponível até mesmo após o encerramento do repositório. O Centro de Desenvolvimento da
Tecnologia Nuclear CDTN está coordenando o projeto para a construção do repositório
nacional para o armazenamento dos rejeitos de baixo e médio nível de radiação. A fim de
consolidar todas as informações que serão provenientes deste projeto, está sendo
desenvolvido e implantado no CDTN um sistema Gerenciador de banco de dados, chamado
de Sistema de Gestão Integrada de dados para Repositórios de Rejeitos Radioativos (SGI3R),
que também vai gerenciar todos os dados de trabalhos anteriores realizados no Brasil e em
todo o mundo sobre este assunto. A proposta é criar uma estrutura de módulos, tendo como
base oito módulos: inventário, seleção de sites, tipos de repositório, tecnologia, parceiros,
legislação, comunicação e documentos. O SGI3R compreende a integração (inclusão,
atualização e exclusão), processamento de dados, padronização e consistência entre os
processos. O SGI3R dará apoio às etapas deste projeto, que permitirá a preservação de todas
as informações disponíveis, evitando a duplicação de esforços e custos adicionais,
melhorando, deste modo, o projeto de planejamento e execução. Adicionalmente o SGI3R
permitirá o acesso às informações para todas as partes interessadas.<br>The implantation of a repository for radioactive wastes is a multidisciplinary project that
demands in addition to specialists of different areas of knowledge, interaction with public and
private institutions, data and information related to radioactive wastes, geology, technology
etc. All the activities must be in accordance with norms, requirements and procedures,
including national and international legislation. The maintenance of the waste inventory
records is an important regulatory requirement and must be available even after the closure of
the repository. The Center of Nuclear Technology Development CDTN is coordinating
the Project for the construction of the national repository to store the low and intermediatelevel
wastes. In order to consolidate all information that will come from this Project, it is
being developed and implanted in CDTN a manager system of database, called Integrated
Management System of data for Radioactive Waste Repositories (SGI3R), which will also
manage all data from previous works carried out in Brazil and around the world about this
subject. The proposal is to build a structure of eight modules: Inventory, Site Selection, Types
of Repository, Documents, Technology, Partners, Legislation, and Communication, having
initially as base the first four ones. The SGI3R comprises the data processing (inclusion,
update and exclusion), integration, standardization, and consistency among the processes. The
SGI3R will give support to the stages of this Project, which will allow the preservation of all
the available information, preventing duplication of efforts and additional costs, improving, in
this way, the Project planning and execution. Additionally the SGI3R will make possible the
information access to all stakeholders.
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Pascual, Christopher C. "Evaporation measurements from simulated nuclear waste storage tanks." Diss., Georgia Institute of Technology, 1996. http://hdl.handle.net/1853/18208.
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Fairlie, Ian. "Radioactive waste : international examination of storage and reprocessing of spent fuel." Thesis, Imperial College London, 1997. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.268029.
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Podruzhina, Tatiana. "Graphite as radioactive waste: corrosion behaviour under final repository conditions and thermal treatment." [S.l.] : [s.n.], 2004. http://deposit.ddb.de/cgi-bin/dokserv?idn=975257641.
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Stoffle, Richard W., Michael J. Traugott, John V. Stone, et al. "Social Assessment of Siting a Low-Level Radioactive Waste Storage Facility in Michigan." School of Natural Resources and Institute for Social Research, The University of Michigan, 1990. http://hdl.handle.net/10150/298951.
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This report presents findings from a social assessment of siting a low level radioactive waste storage facility in Michigan. The research focused specifically on how people perceive themselves to be affected by the proposed facility and the degree of community support for and opposition to the facility. Social assessment research in the LLRW project consisted of a telephone survey of Michigan residents and an in-depth ethnographic survey of residents in the tri-state area of Michigan, Indiana and Ohio. Findings from these studies can aid in the development and implementation of a social monitoring program and in the design of community-based measures to mitigate unwanted social impacts.
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MIYAKE, ELOISA T. "Determinacao da permeabilidade a gas em conceito usado em repositorios para rejeitos radioativos." reponame:Repositório Institucional do IPEN, 1994. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10392.
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FERREIRA, ROBSON de J. "Desenvolvimento de metodologia para a caracterizacao de fontes radioativas seladas." reponame:Repositório Institucional do IPEN, 2010. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9570.
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MOURA, LUIZ A. A. de. "Proposta de implantação de um sistema de gestão ambiental no Laboratório de Rejeitos Radioativos do IPEN-SP." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11508.
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Stoffle, Richard W., David B. Halmo, Henry T. Wright, et al. "Cultural and Paleontological Effects of Siting a Low-Level Radioactive Waste Storage Facility in Michigan." School of Natural Resources and Institute for Social Research, The University of Michigan, 1990. http://hdl.handle.net/10150/305758.
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DELLAMANO, JOSE C. "Otimizacao da etapa de armazenamento de rejeitos radioativos." reponame:Repositório Institucional do IPEN, 2005. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11209.
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Chiu, Yu-yeung. "Environmental radiation monitoring at the low level radioactive waste storage facility in Siu A Chau and development of a particle dispersion model in marine environment." Click to view the E-thesis via HKUTO, 2006. http://sunzi.lib.hku.hk/hkuto/record/B38573611.
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Oxenberg, Tanya Palmateer. "The use of catchboxes to minimize the impact to the environment from testing depleted uranium penetrations." Thesis, Georgia Institute of Technology, 1997. http://hdl.handle.net/1853/18219.
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Pitts, Michelle Lynn. "Design and analysis of subcritical experiments using fresh fuel assemblies." Diss., Georgia Institute of Technology, 1999. http://hdl.handle.net/1853/18375.
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Lautsch, Thomas. "Aktuelle Entwicklung in der Endlagerbranche." Technische Universitaet Bergakademie Freiberg Universitaetsbibliothek "Georgius Agricola", 2017. http://nbn-resolving.de/urn:nbn:de:bsz:105-qucosa-228370.
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Die Endlagerbranche steht vor einem tiefgreifenden Wechsel. Die bisherigen Organisationseinheiten DBE mbH, ASSE GmbH, Bundesamt für Strahlenschutz (BfS) werden neu sortiert und in der neugegründeten Bundes-Gesellschaft für Endlagerung verschmolzen. Eine neue Genehmigungsbehörde, das Bundesamt für Kerntechnische Entsorgungssicherheit (BfE) wird geschaffen. Im Ergebnis dieser Neustrukturierung gibt es eine klare Aufgabentrennung zwischen Regulator und Operator. Darüber hinaus führt die Zusammenlegung der bisher verteilten Aufgaben vom Bauherr und ausführender Baufirma zu Synergieeffekten und einer größeren Umsetzungskompetenz in den Endlagerprojekten. Die neue Bundes-Gesellschaft für Endlagerung (BGE) wird sowohl in der Tiefe als auch in der Breite ihre Aktivitäten jede der bisher bestehenden Organisationen übertreffen und daher eine höhere Schlagkraft haben.
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Courdouan, Merz Amandine. "Nature and reactivity of dissolved organic matter in clay formations evaluated for the storage of radioactive waste /." Zürich : ETH, 2008. http://e-collection.ethbib.ethz.ch/show?type=diss&nr=17723.
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Tourchi, Saeed. "THM analysis of argillaceous rocks with application to nuclear waste underground storage." Doctoral thesis, Universitat Politècnica de Catalunya, 2020. http://hdl.handle.net/10803/670899.
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Argillaceous rocks (Stiff sedimentary clays) provide the geological background to many civil engineering projects. In recent years, interest in these types of material has increased, because they are being considered as potential host geological media for underground repositories of high-level radioactive waste (HLW). The possible use of these types of clay as geological hosts for radioactive waste has prompted the construction of several underground laboratories. Among the very different topics addressed in the Underground Research Laboratories (URLs), the thermo-hydro-mechanical (THM) behaviour of the host rock is the one that most concerns the present research. In situ observations have revealed a considerable number of coupled THM processes in the operation of an HLW repository.
In this context, the main objective of the present study is to describes the performance, observations and interpretation of the full-scale in situ heating test conducted on Callovo-Oxfordian (COx) claystone in the Meuse / Haute-Marne URL simulating a heat-emitting, high-level radioactive waste disposal concept. The test is fully instrumented, and attention is focused on the near-field region's the THM behaviour consisting of the sleeve surrounding the heater and the host rock. The interpretation of the test is assisted by the performance of a coupled numerical analysis based on a coupled formulation incorporating the relevant THM phenomena. The calculations have used a reference isothermal constitutive model especially developed for this type of material. The reference model later has been extended to non-isothermal condition by incorporating thermal dependency of strength parameters and stiffness. The thermomechanical model has been successfully used in the simulation of triaxial tests on COx claystone. The numerical analysis performed has proved able to represent the progress of the experiment very satisfactorily. The performance and analysis of the in-situ test has significantly enhanced the understanding of a complex THM problem and have proved the capability of the numerical formulation and non-isothermal constitutive model to provide adequate predictive capacity.<br>Las rocas argiláceas (arcillas sedimentarias rígidas) proporcionan el trasfondo geológico de muchos proyectos de ingeniería civil. En los últimos años, ha aumentado el interés por este tipo de materiales, porque están siendo considerados como posibles medios geológicos hospedadores de depósitos subterráneos de desechos radiactivos de alta actividad (HLW). El posible uso de este tipo de arcilla como hospedante geológico de residuos radiactivos ha impulsado la construcción de varios laboratorios subterráneos. Entre los muy diferentes temas que se abordan en los Laboratorios de Investigación Subterránea (URL), el comportamiento termo-hidromecánico (THM) de la roca huésped es el que más preocupa a la presente investigación. Las observaciones in situ han revelado un número considerable de procesos THM acoplados en el funcionamiento de un depósito de HLW. En este contexto, el objetivo principal del presente estudio es describir el rendimiento, las observaciones y la interpretación de la prueba de calentamiento in situ a gran escala realizada en piedra arcillosa Callovo-Oxfordian (COx) en la URL de Mosa / Haute-Marne simulando un calor- concepto de eliminación de desechos radiactivos de alto nivel emisor. La prueba está totalmente instrumentada y la atención se centra en el comportamiento del THM de la región de campo cercano que consiste en la manga que rodea el calentador y la roca anfitriona. La interpretación de la prueba es asistida por la realización de un análisis numérico acoplado basado en una formulación acoplada que incorpora los fenómenos de THM relevantes. Los cálculos han utilizado un modelo constitutivo isotérmico de referencia especialmente desarrollado para este tipo de material. Posteriormente, el modelo de referencia se ha ampliado a condiciones no isotérmicas incorporando la dependencia térmica de los parámetros de resistencia y rigidez. El modelo termomecánico se ha utilizado con éxito en la simulación de ensayos triaxiales en arcillas COx. El análisis numérico realizado ha demostrado ser capaz de representar de forma muy satisfactoria el avance del experimento. El rendimiento y el análisis de la prueba in situ ha mejorado significativamente la comprensión de un problema THM complejo y ha demostrado la capacidad de la
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Brown, Ashley Richards. "The impact of ionizing radiation on microbial cells pertinent to the storage, disposal and remediation of radioactive waste." Thesis, University of Manchester, 2014. https://www.research.manchester.ac.uk/portal/en/theses/the-impact-of-ionizing-radiation-on-microbial-cells-pertinent-to-the-storage-disposal-and-remediation-of-radioactive-waste(1935e25b-3bcd-48b8-b2b9-50c33518eb3f).html.
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Microorganisms control many processes pertinent to the stability of radwaste inventories in nuclear storage and disposal facilities. Furthermore, numerous subsurface bacteria, such as Shewanella spp. have the ability to couple the oxidation of organic matter to the reduction of a range of metals, anions and radionuclides, thus providing the potential for the use of such versatile species in the bioremediation of radionuclide contaminated land. However, the organisms promoting these processes will likely be subject to significant radiation doses. Hence, the impact of acute doses of ionizing radiation on the physiological status of a key Fe(III)-reducing organism, Shewanella oneidensis, was assessed. FT-IR spectroscopy and MALDI-TOF-MS suggested that the metabolic response to radiation is underpinned by alterations to proteins and lipids. Multivariate statistical analysis indicated that the phenotypic response was somewhat predictable although dependent upon radiation dose and stage of recovery. In addition to the cellular environment, the impact of radiation on the extracellular environment was also assessed. Gamma radiation activated ferrihydrite and the usually recalcitrant hematite for reduction by S. oneidensis. TEM, SAED and Mössbauer spectroscopy revealed that this was a result of radiation induced changes to crystallinity. Despite these observations, environments exposed to radiation fluxes will be much more complex, with a range of electron acceptors, electron donors and a diverse microbial community. In addition, environmental dose rates will be much lower than those used in previous experiments. Sediment microcosms irradiated over a two month period at chronic dose rates exhibited enhanced Fe(III)-reduction despite receiving potentially lethal doses. The microbial ecology was probed throughout irradiations using pyrosequencing to reveal significant shifts in the microbial communities, dependent on dose and availability of organic electron donors. The radiation tolerance of an algal contaminant of a spent nuclear fuel pond was also assessed. FT-IR spectroscopy revealed a resistant phenotype of Haematococcus pluvialis, whose metabolism may be protected by the radiation induced production of an astaxanthin carotenoid. The experiments of this thesis provide evidence for a range of impacts of ionizing radiation on microorganisms, including the potential for radiation to provide the basis for novel ecosystems. These results have important implications to the long-term storage of nuclear waste and the geomicrobiology of nuclear environments.
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Moura, Luiz Antonio Abdalla de. "Proposta de implantação de um sistema de gestão ambiental no laboratório de rejeitos radioativos do IPEN-SP." Universidade de São Paulo, 2008. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-18052012-092021/.
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Constata-se, atualmente, um uso crescente da energia nuclear no Brasil, para geração de eletricidade e outras aplicações (na medicina, na indústria, em agricultura, em técnicas ambientais, em radio-esterilização). Na realização das atividades de pesquisa do ciclo do combustível nuclear, em outras atividades de pesquisa, nas atividades industriais de produção de combustível e de energia e em todas as aplicações da energia nuclear, são gerados rejeitos radioativos, de atividades alta, média ou baixa. Atualmente, existem técnicas adequadas e seguras para o tratamento e armazenagem desses rejeitos, comentadas neste trabalho e que, sendo aplicadas, facilitam a aceitação da energia nuclear pela Sociedade. Com a crescente preocupação com o meio ambiente, a Organização Internacional de Normalização preparou e emitiu a Norma ISO 14.001 - Sistemas de Gestão Ambiental, aplicável a todos os tipos e portes de organizações, visando a melhoria de seu desempenho ambiental. Seus requisitos foram detalhadamente comentados neste trabalho, sendo particularizados para a sua aplicação no Laboratório de Rejeitos Radioativos do IPEN, como um estudo de caso.<br>An increasing use of nuclear technology in the form of its several applications (electricity generation, medical, industrial, agricultural, environment and radiosterilization) is currently being observed in Brazil. Radioactive waste of high, medium or lower activity is produced in all fuel cycle and other research activities, industrial activities of fiiel production and electricity generation. Appropriate and safe technologies are available for the treatment and storage of radioactive waste and, when applied, contribute for the acceptance of nuclear energy by the Society. With the increasing importance of demands related to environmental issues, the International Organization for Standardization issued the Standard ISO 14.001 - Environmental Management System, applied to all types and size of organizations, helping them to increase their environment performance. In this research, the standard requirements were commented in detail, being particularized to the Laboratory of Radioactive Waste from IPEN, as a case study.
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Leite, Eliana Rodrigues. "Indicadores de segurança para um depósito final de fontes radioativas seladas." Universidade de São Paulo, 2012. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-10122012-102439/.
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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.<br>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.
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MANOCCHI, FABIO H. "Monitoração de Rn-222 nos galpões de armazenamento de rejeitos radioativos do IPEN." reponame:Repositório Institucional do IPEN, 2014. http://repositorio.ipen.br:8080/xmlui/handle/123456789/23275.
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Chiu, Yu-yeung, and 趙汝揚. "Environmental radiation monitoring at the low level radioactive waste storage facility in Siu A Chau and development of a particledispersion model in marine environment." Thesis, The University of Hong Kong (Pokfulam, Hong Kong), 2006. http://hub.hku.hk/bib/B38573611.
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Butterworth, Andrew D. "The utilisation of layered hydroxysalts in the separation, immobilisation and long term storage of long-lived radio-anions of nuclear power legacy waste origin." Thesis, Loughborough University, 2013. https://dspace.lboro.ac.uk/2134/13639.
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Long lived radioactive species such as ¹²⁹I⁻ and ⁹⁹TcO₄⁻ are formed as by-products of nuclear fission. These species have extremely long half-lives (1.5 million and 211,000 years respectively), are biologically assimilating and due to their anionic nature, can move freely within a geosphere. Historical disposal methods for active species are no longer considered acceptable to the general public and other ways in which to treat the waste are being explored. One remove and concentrate method to remove radioactive species from the biosphere is using alkaline-resistant materials which trap active species that can be encapsulated in a high pH concrete matrix. Layered hydroxides and layered double salts which consist of positively charged layers between which exchangeable anions and water molecules lie are good candidates for these materials due to the basic conditions in which they form. The synthesis, anion exchange properties and stability of copper, lanthanum, nickel and zinc hydroxysalts have been investigated. The structures consist of layers of edge-sharing metal hydroxide octahedra together with an interlayer space containing the anion and in some cases water molecules. Products were characterised by powder X-ray diffraction and vibrational spectroscopy to confirm the identity of structure of the material formed and the anion incorporated. Only Cu2(OH)3(NO3), Cu2(OH)3(OAc).H2O, Ni2(OH)3(NO3) and Zn5(OH)3(NO3).2H2O consistently exhibited exchange capabilities with iodide as the target anion. In terms of exchange rate and efficiency, copper hydroxyacetate is a more suitable precursor as equilibrium is achieved in 10 mins; whereas other LHS containing nitrate as the occupying require longer than 1 day to reach equilibrium. Cu2(OH)3(Ac).H2O has been shown to easily exchange acetate for monovalent anions X- (X = Ha-, NO3-, ClO4-, IO4-, SbO3-, OH-). Exchange reactions with ReO4- (used as a surrogate to TcO4-) and trigonal pyramidal monovalent anions (such as IO3-) were unsuccessful. Exposure to divalent anions (CO32-, Cr2O42-, SeO3-) resulted in no interaction whereas exposure to trivalent PO43- forms Cu3(PO4)2. Quantitative analysis has shown that, contrary to XRPD and FTIR data, full exchange of acetate for an equimolar amount of iodide within a Cu2(OH)3+ framework does not occur with 100% efficiency. Activity counting, gravimetric analysis and ion specific probe analysis suggested that only ~92-93% exchange occurs. The stability of TcO4- and I- analogues with respect to pH has been investigated. Activity counting has shown that even in pH 9.5 solution, 57-73% of 125I- and 99TcO4- immobilised with a Cu2(OH)3+ framework is leached into solution after 16 days. Exposure of Cu2(OH)3I to high carbonate, nitrate and chloride environments shows a progressive loss of iodide into solution as the anionic radius of the incoming anion decreases and the concentration of the incoming anion increases. In the case of chloride and nitrate incoming anions, only a 2:1 chloride to iodide ratio is need for full exchange whereas a ratio of 10:1 nitrate to iodide is required. In situ ion exchange experiments at Diamond allowed the exchange of the hydroxyacetate material to be investigated in flow experiments showing similar facile exchange as demonstrated under batch conditions. Rietveld refinements on deuterated samples of halide analogues of the materials have allowed accurate structure determinations for the first time (Cu2(OD)3Cl - a = 5.726Å, b = 6.125 Å, c = 5.634 Å, β = 93.100°, Cu2(OD)3Br - a = 6.085 Å, b = 6.144 Å, c = 5.650 Å, β = 93.593°, Cu2(OD)3I - a = 6.587 Å, b = 6.179 Å, c = 5.680 Å, β = 95.044°). As the size of the halide increases, the hydroxide coordination alters reflecting to changing sigma/pi donor capability of the halide.
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Castro, Adirson Monteiro de. "Avaliação do perfil dos resíduos de serviços de saúde de Belo Horizonte quanto à presença de rejeitos radioativos na destinação final." CNEN - Centro de Desenvolvimento da Tecnologia Nuclear, Belo Horizonte, 2005. http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=26.
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Nenhuma<br>Os procedimentos médicos de diagnóstico e tratamento que utilizam radiofármacos geram rejeitos radioativos que, após decaírem até o limite de eliminação, podem ser destinados pelas vias convencionais de coleta e disposição final de Resíduos Sólidos Urbanos RSU. O objetivo da pesquisa foi detectar radiometricamente a presença de rejeitos radioativos nos resíduos de serviços de saúde destinados à disposição final. Ressalta-se que o limite legal de eliminação para
rejeitos sólidos estabelecido pela Comissão Nacional de Energia Nuclear CNEN é de 7,5 x 104 Bq/kg (2 Ci/kg).
As medições foram feitas no conteúdo de 25 caminhões da coleta especial de Resíduos de Serviços de Saúde (RSS), no aterro sanitário de Belo Horizonte, utilizando-se um cintilômetro de iodeto de sódio. Em 60% dos casos foram encontrados valores acima do limite estabelecido. A
análise espectral de 6 amostras revelou a presença do radionuclídeo tecnécio-99m (99mTc), em 5 delas, e de eodo-131 (131I), em um caso. Estes elementos, tecnécio-99m (99mTc) e iodo-131 (131I), são os mais utilizados em procedimentos de Medicina Nuclear.
Conclui-se que está havendo liberação de rejeito radioativo com os de Resíduos de Serviços de Saúde (RSS), devido a inobservância do tempo de decaimento até obtenção dos níveis legalmente permitidos para liberação.<br>The medical procedures of diagnosis and treatment that use radiopharmaceuticals generate radioactive wastes that can, after reaching the release limit, follow the conventional ways of collection and disposal of the urban solid wastes. This research aims to detect radiometrically the presence of radioactive wastes in the health-care wastes at the final disposal. It is pointed out that the legal limit for the release of solid wastes established by Brazilian National Commission of
Nuclear Energy (CNEN) is 7,5x104 Bq/kg (2 Ci/kg).
Measurements in the material of the garbage trucks that make the special collect from Health Service installations are performed, at Belo Horizonte sanitary landfill, using a NaI scintillation counter. Values above the established limit were found in 60% of the cases. The spectral analysis
of 6 samples showed the presence of 99mTc in 5 of them and 131I in one. These radionuclides are the most common radionuclides used in Nuclear Medicine.
In conclusion there are radioactive wastes released together with the health service wastes, due to the disregard of the decay time until the legal limit is achieved.
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ARAUJO, LEANDRO G. de. "Degradação da resina de troca iônica utilizando o reagente de Fenton." reponame:Repositório Institucional do IPEN, 2013. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10534.
Full textAbstract:
Made available in DSpace on 2014-10-09T12:41:34Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T13:56:02Z (GMT). No. of bitstreams: 0<br>Dissertação (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Glorius, M., H. Moll, G. Bernhard, A. Roßberg, and A. Barkleit. "The Mobilization of Actinides by Microbial Ligands Taking into Consideration the Final Storage of Nuclear Waste - Interactions of Selected Actinides U(VI), Cm(III), and Np(V) with Pyoverdins Secreted by Pseudomonas fluorescens and Related Model Compounds (Final Report BMBF Project No.: 02E9985)." Forschungszentrum Dresden, 2010. http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-27809.
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The groundwater bacterium Pseudomonas fluorescens (CCUG 32456) isolated at a depth of 70 m in the Äspö Hard Rock Laboratory secretes a pyoverdin-mixture with four main components (two pyoverdins and two ferribactins). The dominant influence of the pyoverdins of this mixture could be demonstrated by an absorption spectroscopy study. The comparison of the stability constants of U(VI), Cm(III), and Np(V) species with ligands simulating the functional groups of the pyoverdins results in the following order of complex strength: pyoverdins (PYO) > trihydroxamate (DFO) > catecholates (NAP, 6HQ) > simple hydroxamates (SHA, BHA). The pyoverdin chromophore functionality shows a large affinity to bind actinides. As a result, pyoverdins are also able to complex and to mobilize elements other than Fe(III) at a considerably high efficiency. It is known that EDTA may form the strongest actinide complexes among the various organic components in nuclear wastes. The stability constants of 1:1 species formed between Cm(III) and U(VI) and pyoverdins are by a factor of 1.05 and 1.3, respectively, larger compared to the corresponding EDTA stability constants. The Np(V)-PYO stability constant is even by a factor of 1.83 greater than the EDTA stability constant. The identified Np(V)-PYO species belong to the strongest Np(V) species with organic material reported so far. All identified species influence the actinide speciation within the biologically relevant pH range. The metal binding properties of microbes are mainly determined by functional groups of their cell wall (LPS: Gram-negative bacteria and PG: Gram-positive bacteria). On the basis of the determined stability constants raw estimates are possible, if actinides prefer to interact with the microbial cell wall components or with the secreted pyoverdin bioligands. By taking pH 5 as an example, U(VI)-PYO interactions are slightly stronger than those observed with LPS and PG. For Cm(III) we found a much stronger affinity to aqueous pyoverdin species than to functional groups of the cell wall compartments. A similar behavior was observed for Np(V). This shows the importance of indirect interaction processes between actinides and bioligands secreted by resident microbes.
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Glorius, M., H. Moll, G. Bernhard, A. Roßberg, and A. Barkleit. "The Mobilization of Actinides by Microbial Ligands Taking into Consideration the Final Storage of Nuclear Waste - Interactions of Selected Actinides U(VI), Cm(III), and Np(V) with Pyoverdins Secreted by Pseudomonas fluorescens and Related Model Compounds (Final Report BMBF Project No.: 02E9985)." Forschungszentrum Dresden-Rossendorf, 2009. https://hzdr.qucosa.de/id/qucosa%3A21603.
Full textAbstract:
The groundwater bacterium Pseudomonas fluorescens (CCUG 32456) isolated at a depth of 70 m in the Äspö Hard Rock Laboratory secretes a pyoverdin-mixture with four main components (two pyoverdins and two ferribactins). The dominant influence of the pyoverdins of this mixture could be demonstrated by an absorption spectroscopy study. The comparison of the stability constants of U(VI), Cm(III), and Np(V) species with ligands simulating the functional groups of the pyoverdins results in the following order of complex strength: pyoverdins (PYO) > trihydroxamate (DFO) > catecholates (NAP, 6HQ) > simple hydroxamates (SHA, BHA). The pyoverdin chromophore functionality shows a large affinity to bind actinides. As a result, pyoverdins are also able to complex and to mobilize elements other than Fe(III) at a considerably high efficiency. It is known that EDTA may form the strongest actinide complexes among the various organic components in nuclear wastes. The stability constants of 1:1 species formed between Cm(III) and U(VI) and pyoverdins are by a factor of 1.05 and 1.3, respectively, larger compared to the corresponding EDTA stability constants. The Np(V)-PYO stability constant is even by a factor of 1.83 greater than the EDTA stability constant. The identified Np(V)-PYO species belong to the strongest Np(V) species with organic material reported so far. All identified species influence the actinide speciation within the biologically relevant pH range. The metal binding properties of microbes are mainly determined by functional groups of their cell wall (LPS: Gram-negative bacteria and PG: Gram-positive bacteria). On the basis of the determined stability constants raw estimates are possible, if actinides prefer to interact with the microbial cell wall components or with the secreted pyoverdin bioligands. By taking pH 5 as an example, U(VI)-PYO interactions are slightly stronger than those observed with LPS and PG. For Cm(III) we found a much stronger affinity to aqueous pyoverdin species than to functional groups of the cell wall compartments. A similar behavior was observed for Np(V). This shows the importance of indirect interaction processes between actinides and bioligands secreted by resident microbes.
29
Vuillod, Emmanuelle. "Modélisation thermo-hydro-mécanique de massifs rocheux fracturés : application au stockage de déchets radioactifs." Vandoeuvre-les-Nancy, INPL, 1995. http://www.theses.fr/1995INPL072N.
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Ce travail s'inscrit dans le cadre du projet DECOVALEX (acronyme pour international co-operative project for the development of coupled models and their validation against experiments in nuclear waste isolation) de modélisations thermo-hydro-mécaniques de massifs rocheux fracturés dans lesquels on simule des stockages de déchets radioactifs de haute activité. Résolues analytiquement dans le cas d'un milieu continu (définition d'un milieu équivalent) ou numériquement si le milieu est discontinu (modélisation du comportement des joints), les lois mathématiques qui régissent le comportement du milieu influencent les résultats des modélisations. Les processus couplés THM s'avèrent très influents sur le comportement d'un modèle. Des modélisations avec le code UDEC montrent l'importance des couplages HM selon que les calculs sont menés en régime permanent ou transitoire et l'influence du chemin de chargement dans le cas de modélisations TM. La géométrie de la fracturation influence également le comportement du modèle. Étudier la connexité d'un réseau de fracturation permet de déterminer son degré d'homogénéité. La comparaison de deux méthodes, milieu continu et milieu discontinu, a été menée en déterminant le tenseur de perméabilité et les relations contraintes-déformations sur des éprouvettes fracturées. Elle a ainsi mis en évidence les différences de comportement d'un milieu homogénéisé et d'un milieu discret. Enfin, deux exercices de modélisation THM de sites de stockage de déchets radioactifs illustrent les recherches réalisées. Un modèle en champ lointain a permis de comparer les résultats obtenus par des codes de calculs de logiques différentes. Le second modèle, en champ proche, est davantage axé sur l'importance jouée par la fracturation sur le comportement du massif. La haute densité du réseau de référence a nécessité des développements mathématiques pour déterminer le volume équivalent représentatif (approches continues) et des analyses pour simplifier correctement le milieu (approches discontinues), qui sont ici presentés
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FERREIRA, EDUARDO G. A. "Modelagem descritiva do comportamento do cimento Portland em ambiente de repositório para rejeitos radioativos." reponame:Repositório Institucional do IPEN, 2017. http://repositorio.ipen.br:8080/xmlui/handle/123456789/28423.
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Submitted by Pedro Silva Filho (pfsilva@ipen.br) on 2018-01-31T16:42:14Z
No. of bitstreams: 0<br>Made available in DSpace on 2018-01-31T16:42:14Z (GMT). No. of bitstreams: 0<br>Coordenação de Aperfeiçoamento de Pessoal de Nível Superior (CAPES)<br>A deposição de rejeitos radioativos em repositórios geológicos profundos vem sendo estudada nos últimos anos em diversos países. Materiais à base de cimento são utilizados nesses repositórios como material estrutural, matriz de imobilização de rejeitos ou material de preenchimento. Compreender o desempenho desse material é essencial para garantir a segurança da instalação durante o seu tempo de vida útil (de milhares a centenas de milhares de anos, dependendo do tipo de rejeito). Este trabalho objetiva modelar o comportamento em longo prazo do cimento Portland e estudar a influência de diversos fatores na hidratação e na evolução desse material. A modelagem descritiva abordou a hidratação do cimento nas condições ambientais esperadas no repositório e os efeitos desses fatores em propriedades mecânicas, mineralógicas e morfológicas do cimento. Os fatores ambientais considerados relevantes neste trabalho foram: alta temperatura e pressão, penetração de água subterrânea contendo íons quimicamente agressivos ao cimento e a presença do campo de radiação proveniente dos rejeitos. Ensaios acelerados de degradação também foram realizados para corroborar com o modelo descrito. Observou-se uma sinergia entre diversos fatores na degradação do cimento, como a influência da temperatura e da radiação em reações deletérias ao material. O resultado da modelagem apontou três principais possíveis causas de falha nas barreiras artificiais: a) a formação de um caminho preferencial; b) a perda de resistência e coesão do material; e c) o aumento na corrosão das estruturas metálicas. A descrição do modelo apresentada é a base para a modelagem matemática e a análise de segurança dos repositórios estudados no Brasil.<br>Tese (Doutorado em Tecnologia Nuclear)<br>IPEN/T<br>Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP<br>CAPES:1231206
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FERREIRA, EDUARDO G. A. "Avaliação da alteração nas propriedades da pasta de cimento em ambiente de repositório." reponame:Repositório Institucional do IPEN, 2013. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10208.
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Made available in DSpace on 2014-10-09T12:36:01Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T13:59:48Z (GMT). No. of bitstreams: 0<br>Dissertação (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Manocchi, Fábio Henrique. "Monitoração de Rn-222 nos galpões de armazenamento de rejeitos radioativos do IPEN." Universidade de São Paulo, 2014. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-24092014-132454/.
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Neste trabalho foi avaliada a dose efetiva recebida pelos trabalhadores da Gerência de Rejeitos Radioativos do IPEN devido à inalação de 222Rn nos galpões de armazenamento de rejeitos radioativos tratados e não tratados. As concentrações de 222Rn no interior dos galpões foram determinadas por meio da técnica de detecção passiva com detectores de traços nucleares do estado sólido (SSNTD). O detector utilizado foi o CR-39 inserido em uma câmara de difusão do tipo NRPB. Foram monitorados um total de 12 pontos internos e 1 ponto externo no galpão de rejeitos radioativos tratados G4 e 13 pontos no galpão de rejeitos radioativos não tratados G3, durante um período de 11 meses, entre junho de 2012 e maio de 2013. As concentrações variaram de 0,73 ± 0,08 e 4,55 ± 0,16 kBqm-3 entre os períodos de monitoramento no galpão G4 e entre 0,61 ± 0,07 e 2,94 ± 0,12 kBqm-3 no galpão G3. A dose efetiva devido à inalação de 222Rn no interior dos galpões de rejeitos radioativos foi calculada de acordo com os procedimentos da Comissão Internacional de Proteção Radiológica (ICRP) a partir de um fator de conversão de dose, da concentração média do 222Rn no ar e do tempo de exposição dos indivíduos. Os valores de doses apresentados são uma média das concentrações entre os períodos de monitoramento que variam 15,70 mSva-1 no G4 e de 9,27 mSva-1 no G3, sendo que em um dos períodos obteve-se valores superiores ao estabelecidos pelo órgão regulador (CNEN) e recomendados pela Comissão Internacional de Proteção Radiológica (ICRP) de 20 mSva-1 para indivíduos ocupacionalmente expostos, indicando a necessidade de medidas mitigadoras. Cabe, contudo, informar que foi considerada uma hipótese bastante conservativa de 2000 horas de trabalho no local.<br>Some radionuclides that make up the radioactive series are noted for their contribution to the total exposure to which individuals are subjected, an important example is known as radon 222Rn and their descendants, responsible for more than half of the radiation dose received by the population due to natural sources. In this work the effective dose received by the workers of the Management of Radioactive Waste in IPEN due to inhalation of 222Rn in storage sheds from treated and untreated radioactive waste was evaluated. Concentrations of 222Rn inside the sheds of treated and untreated radioactive waste G3 and G4 were determined by the technique of passive detection with solid state nuclear track (SSNTD) detectors. The detector used was CR-39 inserted in a diffusion chamber type NRPB. A total of 12 internal points and 1 external point were monitored in the shed radioactive waste treated G4 and 13 points in the shed radioactive waste untreated G3, for a period of 11 months between June 2012 and May 2013. Concentrations ranged 0.73 ± 0.08 to 4.55 ± 0.16 kBqm-3 among the monitoring periods in the shed G4 and between 0.61 ± 0.07 and 2.94 ± 0.12 kBqm-3 in the shed G3. The effective dose due to inhalation of 222Rn inside the sheds radioactive waste was calculated according to the procedures of the International Commission on Radiological Protection (ICRP) from a conversion factor of dose, the mean concentration of 222Rn in the air and time of exposure of individuals. The dose values for G4 and G3 are 15.70 and 9.27 mSva-1 respectively, this being greater than the value established by the National Nuclear Energy Commission (CNEN) and recommended by the International Commission on Radiological Protection (ICRP) 20 mSv / a for occupationally exposed individuals, thus indicating the need for mitigation measures. It should, however, report that was considered a very conservative assumption of 2,000 hours of work on site.
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Costa, Sandra Helena Menezes da. "Tratamento e disposição final de resíduos de medicamentos quimioterápicos e de rejeitos radioterápicos: estudo comparativo entre a legislação internacional e a brasileira." reponame:Repositório Institucional da FIOCRUZ, 2010. https://www.arca.fiocruz.br/handle/icict/2465.
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Made available in DSpace on 2011-05-04T12:36:27Z (GMT). No. of bitstreams: 0
Previous issue date: 2010<br>O número de casos de câncer tem aumentado de maneira considerável em todo o mundo, tornando-se um problema de saúde pública mundial. Entre as modalidades terapêuticas para o tratamento câncer estão a quimioterapia e a radioterapia. A quimioterapia é um método que utiliza compostos químicos, chamados quimioterápicos, e a radioterapia é o uso médico de radiação ionizante como parte do tratamento do câncer. Resíduos de quimioterápicos e radioterápicos são considerados perigosos, devido a suas características tóxicas, podendo acarretar riscos ao trabalhador, ao ambiente hospitalar e ao meio ambiente. Mas como é o gerenciamento desses resíduos? Esta dissertação tem como objeto a legislação internacional e nacional vigente, nas áreas de Saúde e Meio Ambiente, visando à luz destas, analisar as diretrizes para o gerenciamento de resíduos de quimioterápicos e radioterápicos, frente aos demais resíduos de serviços de saúde, considerando os riscos intrínsecos destes, no intuito de proteger e preservar a saúde humana e o meio ambiente. Buscou-se discutir se os procedimentos recomendados na literatura científica, para a degradação / inativação, e destinação final destes resíduos estão sendo adotados no Brasil. Como síntese deste trabalho pretende-se contribuir, sugerindo, possíveis alterações na legislação brasileira vigente, das áreas de Saúde e Meio Ambiente, objetivando melhorias na operacionalização e no controle da geração, tratamento e destinação final destes resíduos, através de mecanismos de monitoramento.<br>The number of cancer cases has increased drastically in the world, becoming a worldwide public health problem. Among the therapeutic modalities for cancer treatment are chemotherapycs and radiotherapy. Chemotherapy is a method that uses chemicals, called chemotherapy, and radiotherapy is the medical use of ionizing radiation as part of cancer treatment. Chemotherapy and radiotherapy are considered hazardous due to their toxic characteristics and may result in risks to the worker, the hospital environment and the environment. But how is the management of such wastes? This work studies the international and national laws in force, in the areas of Health and
Environment, in order to analyze the guidelines for management of chemotherapy and radiotherapy, compared to other wastes of health services, considering the in inherent risks, in order to protect and preserve human health and the environment. We tried to discuss if the procedures recommended in the scientific literature for the degradation/inactivation, and disposal of these wastes are being adopted in Brazil. As a summary of this work we intend to contribute, suggesting possible changes in Brazilian legislation, in the areas of Health and Environment, aiming at improvements in
operations and in the generation, treatment and disposal of these wastes through tracking mechanisms.
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SENEDA, JOSE A. "Separação e recuperação de chumbo-208 dos resíduos de tório terras raras gerados na unidade piloto de purificação de nitrato de tório." reponame:Repositório Institucional do IPEN, 2006. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11424.
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Made available in DSpace on 2014-10-09T12:51:45Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:08:59Z (GMT). No. of bitstreams: 0<br>Tese (Doutoramento)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Bulidon, Nicolas. "Etude de la fissuration assistée par l'environnement des aciers peu alliés en situation de stockage géologique des déchets radioactifs." Thesis, Lyon, 2019. http://www.theses.fr/2019LYSEI046/document.
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Le travail mené dans le cadre de cette thèse porte sur l’évaluation de la sensibilité à la fissuration assistée par l’environnement (FAE) d’aciers mis en œuvre pour le stockage géologique profond des déchets radioactifs selon un concept multi-barrières. On s’intéresse ici aux aciers faiblement alliés du conteneur et du chemisage qui seront placés dans des micro-tunnels creusés dans la roche à 500 mètres de profondeur. Le concept actuel prévoit un matériau de remplissage cimentaire entre l’argile et le chemisage afin de neutraliser l’acidité potentielle issue de la re-saturation en eau de la roche après le forage. Malgré la présence d’un milieu peu agressif (pH proche de la neutralité, faible teneur en carbonate), le choix des aciers a été dicté par leur sensibilité à la corrosion et à la FAE, qui est caractérisée dans ce travail. Les microstructures ferrito-perlitiques en bande ont ainsi été éliminées au profit de structures plus homogènes et deux aciers de référence ont été définis : l’API 5L X65 (ferrite-bainite) pour le chemisage et le P285NH (ferrite-perlite) pour le conteneur. Ces études ont également montré la formation de couches de produits de corrosion principalement composées de sidérite et de magnétite conférant une pseudo-passivité. Le caractère protecteur de ces couches vis-à-vis de la fissuration a été étudié et validé, sur la base d’une élaboration de couches représentatives par voie électrochimique. Enfin, les aciers de référence ont été caractérisés du point de vue de leur sensibilité à la corrosion et à la FAE en milieu cimentaire. Ils n’ont alors pas montré de sensibilité particulière du point de vue de la fissuration dans ces conditions, où la corrosion sous dépôt semble être la forme la plus présente en milieu aéré. Néanmoins, l’influence de la présence de faibles teneurs en oxygène dans le concept de stockage doit encore être explorée<br>The aim of the work is to assess the susceptibility to environmental assisted cracking (EAC) of steels used for the deep geological storage of radioactive waste. The storage concept is based on the encapsulation of the waste in a carbon steel containers then placed in micro-tunnels drilled 500 meter deep in Clay. These micro-tunnels are built with a micro-alloyed casing steel. Recently, the storage concept has evolved with the injection of a cementitious bentonite grout between the clay and the casing to balance the potential acidity resulting from the excavation of the micro-tunnels and the gradual saturation of rock with water. Effect of this grout on the risk of corrosion and EAC is also evaluated in the PhD work. In the mild disposal environment considered (pH close to neutrality, low carbonate content), formation of a corrosion product scale composed of siderite and magnetite has been identified. This scale leads to a pseudo-passive state of both steel grades with thus a possible risk of EAC. The risk of EAC was thus first studied and a material selection for the disposal concept was thus first made accordingly. The protective nature of the siderite/magnetite corrosion scale was then studied and reproduced in laboratory using electrochemical techniques. This work allowed for the evaluation of the resistance of each selected steel with respect to general corrosion and EAC. The results did not underlined significant cracking susceptibility of the considered steel grades. Under deposit corrosion seems to be the main form of attack in aerated waste disposal environments but the influence of the presence of low oxygen levels has to be further explored
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Vu-Do, Laurence. "Influence de la matière organique naturelle mobile sur la rétention de l’europium sur l’argilite de Bure." Thesis, Paris 11, 2013. http://www.theses.fr/2013PA112022/document.
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Dans le contexte du stockage profond des déchets radioactifs de haute et moyenne activité à vie longue en France, l’argilite de Bure (Arg) a été choisie comme roche hôte notamment pour ses propriétés de rétention des radionucléides. Or, cette roche argileuse dite du Callovo-Oxfordien (COx) contient naturellement de la matière organique (MO). Le but de cette thèse est d’évaluer l’influence de la MO naturelle mobile sur la rétention sur l’argilite de l’europium, analogue classique des actinides trivalents des déchets vitrifiés. Trois molécules organiques sont étudiées : les acides subérique, sorbique et tiglique, acides organiques de faible poids moléculaire identifiés dans l’eau porale naturelle du COx. Toutes les expériences ont été réalisées dans un milieu simulant l’eau du COx (pH=7,5 ; I=0,1 mol/L ; PCO2 =10^(-2) bar).La caractérisation de notre échantillon d’argilite montre sa conformité avec les études précédentes de la zone d’intérêt et que le pH de 7,5 est incontournable pour ne pas dénaturer la roche. L’étude du système Eu-MO montre que les acides organiques n’ont pas d’influence sur la spéciation de l’europium dans l’eau de COx. L’étude expérimentale de l’interaction Eu-Arg confirme que la rétention se fait par sorption sur l’argilite (CEu<6.10-6mol/L) et précipitation dans l’eau de COx (CEu>6.10^(-6)mol/L). Le coefficient de distribution Rd, qui quantifie la sorption, est de 170 ± 30 L/g, valeur élevée conforme aux valeurs documentées sur des argilites naturelles. Enfin, l’étude du système ternaire Eu-MO-Arg montre une légère augmentation de la rétention de Eu en présence de matière organique. Cet effet synergique est très satisfaisant du point de vue de la sûreté du stockage : la présence de ces petits acides organiques naturels ne remet pas en question les propriétés de rétention de l’argilite vis-à-vis de l’europium et des actinides trivalents<br>Bure clay rock (CR) was chosen as host rock for the French high and intermediate level long lived radioactive waste repository. This choice is mostly explained by the retention ability of the Callovo-Oxfordian rock (COx). Bure clay rock contains natural organic matter (OM) that could have an influence on radionuclide retention. The aim of this work is to assess the influence of natural mobile OM on the retention of Eu on clay rock. Eu was chosen as a chemical model for trivalent actinides contained in vitrified waste. Three organic molecules were studied: suberic, sorbic and tiglic acids, small organic acids identified in COx pore water. All the experiments were carried out in an environment recreating COx water (pH=7.5 ; I=0.1 mol/L ; PCO2 =10^(-2) bar).Clay rock sample characterization showed that the sample used in this work was similar to those previously extracted from the area of interest and that it was necessary to maintain pH at 7.5 to avoid altering the clay rock. The Eu-OM system study indicated that organic acids had no influence on Eu speciation in COx water. The Eu-CR system experimental study confirmed that retention implied sorption on CR (CEu<6.10^(-6)mol/L) and precipitation in COx water (CEu>6.10-6mol/L). Distribution coefficient Rd (quantifying sorption) was estimated at 170 ± 30 L/g. This high value is consistent with literature values obtained on clay rocks. The ternary Eu-OM-CR system study showed a slight increase of sorption in the presence of organic matter. This synergistic effect is very satisfactory in terms of storage security: the presence of small organic acids in clay rock does not question retention properties with respect to europium and trivalent actinides
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Park, Sang-Hoon. "Contribution a l'etude du comportement de materiaux colmatants dans une fissure : experiences en laboratoire avec une montmorillonite sodique dans une fissure simulee." Paris, ENMP, 1987. http://www.theses.fr/1987ENMP0043.
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Etude en laboratoire du comportement de la bentonite green-bond dont on envisage l'usage dans les remblais de forages de sites de stockage de dechets radioactifs. On etudie en particulier le gonflement de l'argile avec de l'eau, son erosion par un ecoulement d'eau demineralisee. On procede a la reconnaissance de l'influence des processus chimiques sur le comportement de l'argile, les phenomenes d'erosion n'apparaissant que pour des forces ioniques faibles et donc des conductivites faibles
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Verron, Heloïse. "Étude expérimentale des interactions matériau cimento-bentonitique / argilite / fer et acier (MREA/COx/Fe ou acier) à 90°C en conditions de stockage géologique profond des déchets radioactifs (CIGEO)." Electronic Thesis or Diss., Université de Lorraine, 2020. http://www.theses.fr/2020LORR0205.
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Dans le concept actuel de stockage de déchets radioactifs en couche géologique profonde tel qu’envisagé par l’Andra (projet CIGEO), les colis de déchets sont placés dans des alvéoles creusées dans l’argilite du Callovo-Oxfordien (COx) dont le chemisage est en acier faiblement allié. Le COx, et en particulier les pyrites qui le composent, peuvent s’oxyder lors du creusement. Grâce à un montage expérimental original, impliquant plusieurs mélanges pyrite/minéral et un réacteur couplé à un micro chromatographe en phase gazeuse, il est démontré, sur la base de la consommation d'O2 mesurée, qu'à 100°C en présence de calcite, moins de 50% de la pyrite est oxydée. Cette oxydation implique une acidité susceptible de corroder le chemisage des alvéoles. L’Andra a donc développé et breveté un coulis cimento-bentonitique bas pH (9<br>In the current concept of radioactive waste deep geological disposal planned by Andra (CIGEO project), waste containers are stored into disposal cells drilled into the Callovo-Oxfordian claystone (COx) and encircled by a carbon steel liner. COx and in particular its pyrites, can be oxidized during the drilling of cells. Thanks to an original experimental set-up, involving several pyrite/mineral mixtures and a reactor coupled to a micro gas chromatograph, it is demonstrated, based on the measured O2 consumption that at 100°C in presence of calcite, less than 50% of the pyrite is oxidized. This oxidation induces a transient acidic plume and consequently the corrosion of the steel liner. Andra has developed and patented a low-pH (9
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Smati, Abdenasser. "Contribution à l'étude des transferts de chaleur et de masse dans le matériau de remplissage d'un stockage de déchets haute activité." Paris 6, 1986. http://www.theses.fr/1986PA066143.
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La connaissance des phénomènes d'hydratation du matériau de remplissage est essentielle pour une prédiction des transferts dans les barrières ouvragées des stockages de déchets radioactifs en milieu géologique. On a développé, dans le cas isotherme, une méthode thermique de mesure continue de l'humidité sur des échantillons d'argile compactée. Cette méthode a été utilisée pour déterminer le coefficient de diffusion et la perméabilité d'un matériau argileux non gonflant (kaolinite). Son application à la bentonite (smectite) demande des développements supplémentaires du fait de la complexité du comportement de ce matériau.
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Beziat, Alain. "Etude experimentale de la conductivite thermique de materiaux argileux hautement compactes : contribution a l'etude du stockage de dechets radioactifs." Orléans, 1987. http://www.theses.fr/1987ORLE2026.
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Etude de l'influence de densite, teneur en eau, temperature, et aussi des caracteristiques mineralogiques et des conditions physiques externes (accroissement de temperature, contrainte mecanique). Amelioration de la conductivite par additifs (graphite, quartz). Utilisation de modeles pour relier la conductivite a celles de chaque phase; bons resultats obtenus avec le modele geometrique (empirique) et le modele de porosite ellipsoidale
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Dufournet, Françoise. "Adaptation des ciments magnesiens au stockage souterrain des dechets nucleaires." Paris, ENMP, 1987. http://www.theses.fr/1987ENMP0088.
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Une etude de la composition mineralogique des ciments fait apparaitre un enrichissement en mgo et un appauvrissement en mgcl::(2) et en eau. La maniabilite, avant prise, est regie par la teneur en mgcl::(2). Les ciments riches en mgo varient beaucoup avec leur composition. Deux ciments de composition tres differente sont soumis a lessivage intensif en soxhlet double. Cela provoque l'augmentation de la permeabilite et la migration des acces de pores vers des acces plus gros pour l'un des ciments et l'inverse pour l'autre qui est un ciment hypermagnesien
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Muthuraman, M. "Studies On Titanate Based Multi-Phase Ceramics : Prospective Radioactive Waste Storage Materials." Thesis, 1996. http://etd.iisc.ernet.in/handle/2005/1686.
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Ramachandran, Subbaratnam. "Heat transfer and modelling studies for the analysis of waste storage facilities." 1985. http://hdl.handle.net/2097/27520.
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Hung, Li-Chi, and 洪立齊. "Study of Multi-stage Administrative Procedure: Focused on Final Disposal Procedure of Radioactive Waste." Thesis, 2015. http://ndltd.ncl.edu.tw/handle/4yc8bh.
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碩士<br>國立臺北大學<br>法律學系一般生組<br>103<br>ABSTRACT
Study of Multi-stage Administrative Procedure: Focused on Final Disposal Procedure of Radioactive Waste
by
HUNG, LI-CHI
July 2015
ADVISOR(S)：Dr. CHANG, HUEI-TUNG
DEPARTMENT：DEPARTMENT OF LAW
MAJOR：PUBLIC LAW
DEGREE：MASTER OF LAWS
In the modern society featured by information explosion and rapid change of all things, the need of people increases and State missions become diverse. It’s hard to image that only one agency deals with one single affair at one time. Thus, the phenomenon of multi-agency, multi-process, and multi-disposition has become one of the characteristics of the pluralistic society. It’s helpful for administrative tasks, but also generates lots of problems relevant to the rights and obligations of legal relations, such as the distinction between legal concepts and the right to relief. These problems are under intense debate both in practice and doctrine.
Meanwhile, the current operation of nuclear power plants in the country produce lots of nuclear waste, and how to resettle these radioactive waste has already caused considerable controversy. Facing with the current status of radioactive waste management such as problems concern nuclear safety regulation, radiation protection, radiation detection and other environmental issues, final disposal of radioactive waste is of most importance. Regardless of whether to adopt the policy of non-nuclear homeland, our Country's radioactive waste required to be properly handled. In addition to the storage at nuclear power plants and the Nuclear Energy Institute, radioactive waste of Taiwan are also partly stored in Lanyu. The fact causes discussions concerning aboriginal interests, maintenance of environmental justice, due process, and nuclear safety. The questions above are worth pondering, it is the opinion of this thesis that establishment of legal system in Taiwan may be able to reduce such struggle and to avoid such conflict as Lanyu storage site in the future.
As a precaution, the establishment, operations and abolishment on final disposal facility of radioactive waste, which are so complex and involve with public interests, solutions and discussions should be participated by the parties. This thesis also expect to observe from the viewpoint of multi-stage administrative procedures, and to find out how the decision were made between various stages of disposal of radioactive waste and how to protect people's rights of relief. In addition, through the comparison of foreign-related legal system, to discover the blind spot under the current relevant legal final disposal of radioactive waste might be possible. Through a series of speculative process, this thesis expects that there is a better understanding on the concept of multi-stage administrative procedures, and help to make programming of the disposal of radioactive waste towards the right path.
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Podruzhina, Tatiana [Verfasser]. "Graphite as radioactive waste: corrosion behaviour under final repository conditions and thermal treatment / vorgelegt von Tatiana Podruzhina." 2004. http://d-nb.info/975257641/34.
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Ping-Chen, Chu, and 朱炳珍. "Application of Analytic Hierarchy Process (AHP) in the Evaluation ＆ Selection of Low Level Radioactive Waste Final Disposal Site." Thesis, 2001. http://ndltd.ncl.edu.tw/handle/29460742098932923357.
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碩士<br>元智大學<br>工業工程研究所<br>89<br>The final disposal of low level radioactive waste becomes an important issue for people in Taiwan and it is also a key factor for the construction of the 4th Nuclear Power Plant. To properly dispose of low level radioactive waste and to isolate the waste from our living environment will meet the safe and clean requirements in using nuclear energy. Before constructing a final disposal site, a proper site must be selected carefully. There are many complicated factors in selecting a site. These factors involves such as natural conditions, environmental impact, social and economical considerations, etc. with both qualitative and quantitative properties that are mixed in the evaluation criteria. The AHP (Analytic Hierarchy Process) provides an approach to establish a set of useful evaluation model to achieve neutrality and feasibility during evaluation process. This study uses the AHP as an analytical tool to facilitate the group’s decision making from a team with scholars and experts. First of all, the questionnaires of Delphi method were used to establish evaluation criteria and to form a hierarchical structure. Then, through the integration of scholars and experts’ decisions, a pairwise comparison matrix was obtained. By using the AHP software, Expert Choice, which can perform calculations, consistency test, and sensitivity analysis. Finally, a rank of the site alternatives was selected according to priorities. In simulating five sites case study, case D has the highest priority of 0.315 and followed by case E with a priority of 0.242. Both cases are offshore islands as suggested. It was suggested that a site selection should have offshore islands considered first. Among the evaluation criteria the public safety, community communication, and resident acceptance are three most important critical criteria. It indicates that a decision-making authority must provide the safety assurance and communication with the public in order to make a successful site selection.
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Kao, Yu-Yen, and 高宇彥. "Theory and Practice of Referendum ─ Focused on the Low-level Radioactive Waste Final Disposal Facility Site Settings Ordinance." Thesis, 2013. http://ndltd.ncl.edu.tw/handle/56042415296564496369.
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碩士<br>中原大學<br>財經法律研究所<br>101<br>Citizen participate in national affairs the most direct means of way is "referendum". That is, the citizens in the most direct way of the vote for the issues support or oppose the minority is subordinate to the majority, and the results for decision-making units or government can produce a restraint or reference effect, and thus achieve the democracy of the sovereignty of the people. The doctrinal believe that the referendum can make up for the inadequacy of the political representative. But in fact, if the referendum is a very good system and the way directly through a referendum to resort to public opinion to decide the major policies of the country should be able to directly show the demeanor of a democratic country should have, but why community citizens polling place to hold the view there is still considerable disagreement? many issues which are worth exploring.
Legislative Yuan passed the referendum law in November 2003, effective January 2, 2004. Six national referendums have been held up to 2008, but six did not pass; local referendum, like the 25-a-side small class referendum in Kaohsiung and the case of Penghu Game referendum which basis on Islands Construction Act are losing, even certain referendum proposal, not yet formed motion Referendum Review Committee rejected .
In this paper, sort out the European and American countries in the democratic development and citizen voting movement of the development of the course to collect citizen voting-related legal information summarized and analyzed to explore the "low-level radioactive waste final disposal facilities field address set Article Ordinance development included in the follow-up to the referendum mechanism for amending the law.
Delivery of major national policy referendum not only accurately reflect public opinion, is best achieved direct democracy, if the state before crucial policies to promote deliberate public opinion, to not only establish the direction of the governance of the country in line with the expectations of the people, for the people's democratic the enhancement of literacy, there are substantial benefits. Just reimbursing depending on the referendum as a plague, that the so-called experts reject the referendum, this is the right way of governing the country with authoritarian totalitarian regimes such as North Korea there is no difference.
It is looking forward to through this article to view the current referendum mechanism, and proposed amending the law suggested content for many of the limitations of the existing referendum law, establish a model of direct democracy.
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林心睿. "The interaction between interest group and deliberative democracy: Case study of public forum for low-level radioactive waste final disposal siting." Thesis, 2011. http://ndltd.ncl.edu.tw/handle/30671981662321609793.
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碩士<br>國立政治大學<br>公共行政研究所<br>99<br>Deliberative democracy emphasizes citizen-orientation in decision-making and pluralist democracy emphasizes interest groups’ influence on public policy. Since both citizens and interest groups are important components of civil society, this article focuses on the interaction between deliberative democracy and interest groups in policy participation.
This research takes “Public Forum for Low-level Radioactive Waste Disposal Siting” as the empirical case and explores it by secondary data and in-depth interview.
The findings are as follow:
1. The reasons for government to adopt public deliberation as policy tool were to face the obstacles in communication process, to increase social discussions in this issue, to build up a new communication platform, and to disclose accurate information to the public.
2. The motives for interest groups to participate deliberative process are monitoring public forum, providing accurate information, and attempting to create new forms of public participation. Nevertheless, there are also some concerns which might cause interest groups’ unwillingness to participate the deliberative process, including their prior experiences of interacting with governments, the maintenance of group autonomy, and uncertain effects from deliberative process.
3. This study shows that both interest groups and deliberative democracy have mutual effect deliberative process.
4. Deliberative process in the interaction could enhance civic competence, but restrict the voice from social minority; in the dimension of the institutional design, deliberative process can help interest groups collect necessary information, but limit the scopes of policy issues for discussion. Finally, there is no apparent evidence supporting that interest groups and deliberative democracy process can make decision making difference.
In the end, this study proposes that the governments should strengthen information disclosure, build infrastructure regarding deliberative democracy as well as promote deliberative activities.
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Nadarajah, Parthiban. "Chemistry and Corrosion Mechanisms of Steels Embedded in High-density Slag Concrete for Storage of Used Nuclear Fuel." Thesis, 2011. http://hdl.handle.net/1807/31361.
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The chemistry and corrosion mechanisms associated with reduced sulfur compounds such as calcium sulfide, present in ground granulated blast-furnace slag (GGBFS), have been studied in high-density concrete, mortar and simulated pore-water environments. The high-density concrete and mortar samples were produced to replicate the high-density GGBFS concrete, in the dry storage containers (DSCs), used for radiation shielding from used nuclear fuel. Electrochemical measurements on embedded steel electrodes in high-density GGBFS concrete and mortar samples, showed that sulfide is capable of consuming oxygen to create a stable, reducing environment, though not in all cases, and the high-frequency electrolyte resistance increases with hydration time. Ion chromatography on simulated pore-water environments determined that thiosulfate is quite kinetically stable as a sulfide oxidation product and magnetite is capable of oxidizing sulfide. Microscopy has also been used to provide visual evidence of GGBFS hydration and elemental quantification of the hydrating microstructure in different environments.