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Dissertations / Theses on the topic 'Uranium hexafluoride'

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Published: 4 June 2021

Last updated: 17 June 2025

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1

Freestone, Nigel Phillip. "Purification of uranium hexafluoride by non-aqueous means." Thesis, University of Leicester, 1987. http://hdl.handle.net/2381/33682.

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This work has shown that nitrogen dioxide will selectively remove uranium hexafluoride from a mixture containing the hexafluorides of uranium, molybdenum and tungsten via the formation of nitrylium hexafluorouranate(V). The production of lower uranium fluorides and elemental sulphur or sulphur fluorides from many of the attempted preparations of uranium(VI) thiofluorides was predicted from a thermodynamic study of the stabilities of MC1nF6-n (M = U, Mo, W; n = 1-5), MOnF6-2n' MSnF6-2n (M = U, Mo, W; n = 1 or 2) with respect to decomposition and disproportionation. Sorption of the liquid hexafluorides on various potential sorbents was investigated. Encouraging results were obtained for cryolite. Salts such as ARuF6 (A = K, Rb, NH4) were synthesised by direct interactions between AF and RuF5 in AHF. These reactions were found to require the presence of a polar solvent. It was found that ruthenium pentafluoride in liquid uranium hexafluoride could be removed by the Introduction of trace quantities of water.

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2

ARAUJO, ENEAS F. de. "Purificacao de hexafluoreto de uranio." reponame:Repositório Institucional do IPEN, 1986. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9876.

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3

Achour, Mickaël. "Mécanisme de corrosion du fer par UF₆ liquide à 80°C." Thesis, Université Paris-Saclay (ComUE), 2018. http://www.theses.fr/2018SACLS064.

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Le combustible nucléaire utilisé dans les réacteurs actuels doit répondre à une spécification de composition en ²³⁵U différente de celle de l’uranium naturel. Il est alors nécessaire de procéder à un enrichissement en part fissile avant de fabriquer le combustible utilisé en réacteur. Cet enrichissement est réalisé par centrifugation en phase gaz en utilisant l’uranium sous forme d’hexafluorure d’uranium UF₆. Ce composé clé est fabriqué par l’usine COMHUREX à partir de UF₄, et doit répondre à des exigences de pureté, et sa manipulation, à des exigences de sécurité. Cette molécule est très réactive sous forme gazeuse ou liquide et une corrosion du dispositif industriel métallique est constatée. Cette corrosion doit être étudiée afin d’envisager la pollution causée par les produits de corrosion ou encore la durée de vie de l’installation. L’enjeu de cette thèse est de combler les insuffisances de la littérature sur la question de la corrosion par UF₆ liquide à 80°C, qui n’a jusqu’alors pas fait l’objet de recherches publiées. Des équipements adaptés à la réalisation d’essais de corrosion en milieu nucléaire, à 80°C et 3 bars de pression, et des procédures anoxiques d’analyses de ces essais ont dû être mis en place. La réalisation d’essais de corrosion du fer, matériau modèle, par UF₆ liquide à 80°C a ensuite pu être entreprise afin de déterminer la nature des produits de corrosion, la structure de la couche de corrosion et la cinétique de la réaction entre le fer et UF₆ liquide à 80°C. Ces informations ont pu permettre une réflexion sur le mécanisme de corrosion. Ce manuscrit présente le dispositif et la procédure d’essai mise en place permettant la réalisation d’essais de corrosion puis les résultats obtenus. La nature et la structure de la couche de corrosion ont été obtenues grâce aux précautions anoxiques utilisées tout au long des essais réalisés. Deux comportements distincts sont observés. L’origine expérimentale de cette divergence est discutée. La réflexion sur les observations expérimentales, telles que la nature ou les rapports d’épaisseurs des différentes couches, permet de proposer différentes hypothèses sur le mécanisme de corrosion. Un mécanisme de corrosion du fer par UF₆ liquide à 80°C est donc proposé<br>The nuclear fuel used in today’s power plants requires a precise uranium isotope composition which is different from natural uranium. Thus, an enrichment process is required, for which gaseous centrifugation is employed using uranium hexafluoride (UF₆). This compound is obtained by fluorination of UF₄ and its handling is submitted to security issues. This compound is highly reactive, in gaseous or liquid state, and the metallic industrial production setup is corroded, leading to solid residues at process temperatures. This corrosion has to be considered in order to predict both the process efficiency (purity, output) and the resulting industrial issues (setup lifetime, corking). This study aims at understanding liquid uranium hexafluoride corrosion at 80°C, which remains unstudied to this day. A dedicated novel test setup along with adapted analysis precautions have been developed in order to perform reliable experiments and corrosion products identification, since those products and UF₆ are moisture sensitive. This study mostly focused on the corrosion of iron as a model material in liquid UF₆. The experimental results obtained, allowed us to follow the evolution of the structure and the nature of the corrosion layer. Two different kinds of layer have been observed and the experimental origin of this divergence is discussed. With those experimental results, a corrosion mechanism is suggested for the corrosion of iron in liquid uranium hexafluoride at 80°C

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4

KOMATSU, CINTIA N. "Diretrizes para avaliação do gasto ambiental no ciclo do combustivel nuclear." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11712.

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5

Harris, Joseph B. "Evacuation and Shelter in Place Modeling for a Release of Uranium Hexafluoride." Digital Commons @ East Tennessee State University, 2014. https://dc.etsu.edu/etd/2351.

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Evacuation and sheltering behaviors were modeled for a hypothetical release of uranium hexafluoride (UF6) from Nuclear Fuel Services (NFS) in Erwin, Tennessee. NFS down-blends weapons grade Cold War-era nuclear fuel material and processes highly-enriched uranium occasionally using UF6 onsite. Risk associated with a chemical release to the surrounding residential population was assessed by running 2 scenarios involving an airborne release of UF6 to compare evacuation and sheltering in place actions as effective survival strategies. Risk is minimal and evacuation is recommended for people within a 2-mile radius of the release point. Shelter in place actions are recommended for all critical facilities that have the potential to be affected by a chemical release plume. Oak Ridge National Laboratory’s Radiological Assessment System for Consequence Analysis and Capacity-Aware Shortest Path Evacuation Routing in conjunction with a geographic information system proved to be valuable technological tools in determining evacuation routing and exposure zones.

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6

MARCHESINI, PAULO R. de A. "Diagnóstico e sugestões para a gestão do conhecimento aplicada a uma instalação nuclear: a unidade de produção de hexafluoreto de urânio." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11684.

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7

Downing, Edward Nicolas. "Surface studies of the adsorption and heterogeneous decomposition of UFâ†6 on well characterised surfaces with reference to U CVD." Thesis, University of Oxford, 1998. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.298233.

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8

MATTIOLO, SANDRA R. "Diretrizes para implantação de um sistema de gestão ambiental no ciclo do combustível nuclear: estudo de caso da USEXA-CEA." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10169.

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9

SANTOS, IVAN. "Descomissionamento de uma usina de producao de hexafluoreto de uranio." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11758.

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10

SANTOS, LAURO R. dos. "Unidade piloto de obtencao do tricarbonato de amonio e uranilo." reponame:Repositório Institucional do IPEN, 1989. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10220.

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11

SILVA, TERESINHA de M. da. "Contribuição ao estudo da nova filosofia internacional de segurança radiológica no processamento químico do urânio natural." reponame:Repositório Institucional do IPEN, 1988. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9905.

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12

OLIVEIRA, DIRCEU P. de. "Estudo da correlacão entre normas da Agência Internacional de Energia Atômica e de mercado sobre sistema de gestão aplicável à operação de plantas de conversão de UFsub(6)." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11721.

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13

BEDIA, CARLOS E. M. de. "Gestão do conhecimento organizacional através da identificação e análise das competências essenciais: o caso USEXA." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11650.

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14

Benzouaa, Rachid. "Purification de l'hexafluorure d'uranium." Thesis, Clermont-Ferrand 2, 2014. http://www.theses.fr/2014CLF22433.

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L’hexafluorure d’uranium (UF6), est le seul composé utilisé à l’état gazeux dans les procédés d’enrichissement pour la production du combustible nucléaire. Pour le bon déroulement de l’étape d’enrichissement, la qualité de UF6 est primordiale. Cette étude s’est intéressée principalement aux impuretés volatiles sous forme de fluorures et oxyfluorures et leur réactivité avec des matériaux en présence ou non de l’UF6. La nature des produits adsorbés et de réactions a été identifiée. Les mécanismes physico-chimiques mis en jeux lors de la sorption ont été investigués. Les performances (capacité de sorption, sélectivité et régénération) de ces matériaux absorbants et adsorbants ont été évaluées en vue de leur utilisation comme filtre UF6 dans les usines de conversion<br>Uranium hexafluoride (UF6), is the only compound used in the gaseous state in the process of enrichment to produce nuclear fuel. For the success of the enrichment step, the UF6 quality is paramount. This study is mainly concerned with volatile impurities in form of fluorides and oxyfluorides and their reactivity with the materials in presence or not of UF6. The nature of the adsorbed compounds and reactions products was identified. The physico-chemical mechanisms of sorption were investigated. The performances (sorption capacity, selectivity and regeneration) of the absorbent and adsorbent materials have been evaluated to be used as UF6 filters in conversion plants

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15

MARIN, MARISTHELA P. de A. "Analise de perigos em uma instalacao de producao de hexafluoreto de uranio." reponame:Repositório Institucional do IPEN, 1999. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10763.

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NEGRO, MIGUEL L. M. "Desenvolvimento de um modelo para dimensionamento da capacidade produtiva de fábricas de combustível nuclear para reatores de pesquisa." reponame:Repositório Institucional do IPEN, 2017. http://repositorio.ipen.br:8080/xmlui/handle/123456789/28038.

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Submitted by Pedro Silva Filho (pfsilva@ipen.br) on 2017-11-22T17:00:26Z No. of bitstreams: 0<br>Made available in DSpace on 2017-11-22T17:00:26Z (GMT). No. of bitstreams: 0<br>Conselho Nacional de Desenvolvimento Científico e Tecnológico (CNPq)<br>A demanda por combustível nuclear para reatores de pesquisa está aumentando em nível mundial, enquanto várias de suas fábricas têm pequeno volume de produção. Este trabalho estabeleceu um modelo conceitual com duas estratégias para o aumento da capacidade produtiva dessas fábricas. Foram abordadas as fábricas que produzem elementos combustíveis tipo placa carregados com LEU U3Si2-Al, tipicamente usados em reatores nucleares de pesquisa. A primeira estratégia baseia-se na literatura da área de administração da produção e é uma prática frequente nas fábricas em geral. A segunda estratégia aproveita a possibilidade de desmembrar setores produtivos, comum em instalações de produção de combustível nuclear. Ambas as estratégias geraram diferentes cenários de produção, os quais devem ser seguros em relação à criticalidade. Foram coletados dados de uma fábrica real de combustível nuclear para reatores de pesquisa. As duas estratégias foram aplicadas a esses dados com a finalidade de testar o modelo proposto, o que configurou um estudo de caso. A aplicação das estratégias aos dados coletados deu-se por meio de simulação de eventos discretos em computador. Foram criados diversos modelos de simulação para abranger todos os cenários gerados, de forma que o teste indicou um aumento da capacidade produtiva de até 207% sem necessidade de aquisição de novos equipamentos. Os resultados comprovam que o modelo atingiu plenamente o objetivo proposto. Como principal conclusão pode-se apontar a eficácia do modelo proposto, fato que foi validado pelos dados da fábrica.<br>Tese (Doutorado em Tecnologia Nuclear)<br>IPEN/T<br>Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP<br>CNPq:310274/2012-5

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FERREIRA, NELSON L. D. "Aplicação dos conceitos de indivíduo representativo e de grupo crítico para o controle ambiental de instalações nucleares no Brasil." reponame:Repositório Institucional do IPEN, 2014. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11805.

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18

Clarenc, Romain Pierre. "Synthèse et caractérisation de composés fluorés pour le piégeage de fluorures gazeux." Thesis, Bordeaux 1, 2010. http://www.theses.fr/2010BOR14094/document.

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Ce travail porte sur la synthèse et la caractérisation de fluorures à base d’alcalins, d’alcalinoterreuxet de terres rares et sur la réactivité de ces composés vis-à-vis de ReF6 pour lapurification de UF6. L’étude traite dans un premier temps de la synthèse de fluorures tels queKMgF3, MgF2 et CaF2 en couplant une voie solvothermale assistée par micro-ondes et uneétape de fluoration à partir de fluor élémentaire (F2). Les techniques de caractérisationutilisées mettent notamment en avant le caractère basique au sens de Lewis de ces composéset la possibilité de contrôler leur surface spécifique et leur taux d’oxygène, à l’origine dessites basiques, via la température de fluoration (F2) en phase gaz. Dans un second temps, lasolution solide Ce1-xZrxF4 à base de Ce4+ et Zr4+ a été obtenue par fluoration directe d’oxydesmixtes à partir de fluor élémentaire dilué. L’étude par DRX et RMN du 19F montre laprésence d’une solution solide pour des compositions voisines de x=0,5. Enfin, la réactivité deReF6 et UF6 sur KMgF3, MgF2 et CaF2 montre que KMgF3 est un très bon candidat pour lapurification de UF6 vis-à-vis de ReF6, qui dépend à la fois de paramètres intrinsèques auxfluorures divisés (surface spécifique, taux d’oxygène, basicité, cations mis en jeu…) maisaussi du procédé de purification (température, temps de contact)<br>This work deals with the synthesis and characterization of alkali, alkali-earth and rare earthbased fluorides and the reactivity of the latter with ReF6 for UF6 purification. In a first part,we focused our attention on the synthesis of KMgF3, MgF2 and CaF2 high surface area metalfluorides coupling both microwave assisted solvothermal process and a fluorination step withelemental fluorine (F2). The higher the surface area, the higher the oxygen rate. Thesenanofluorides exhibit Lewis basic character. In a second part, several compositions of theCe1-xZrxF4 solid solution were synthesized by direct fluorination of mixed oxides usingelemental fluorine (F2). XRD an 19F NMR characterizations show the occurence of a newsolid solution for compositions close to x=0.5. Finally, the reactivity between ReF6/UF6 andKMgF3, MgF2 and CaF2 leads to conclude that KMgF3 is the best candidate for thepurification of UF6. This study indicates that the purification depends on several parameters :intrinsic parameters of the divided fluorides (surface area, oxygen rate, basicity, cations…)and parameters directly related to the process (temperature, contact time)

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Negro, Miguel Luiz Miotto. "Desenvolvimento de um modelo para dimensionamento da capacidade produtiva de fábricas de combustível nuclear para reatores de pesquisa." Universidade de São Paulo, 2017. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08112017-090700/.

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A demanda por combustível nuclear para reatores de pesquisa está aumentando em nível mundial, enquanto várias de suas fábricas têm pequeno volume de produção. Este trabalho estabeleceu um modelo conceitual com duas estratégias para o aumento da capacidade produtiva dessas fábricas. Foram abordadas as fábricas que produzem elementos combustíveis tipo placa carregados com LEU U3Si2-Al, tipicamente usados em reatores nucleares de pesquisa. A primeira estratégia baseia-se na literatura da área de administração da produção e é uma prática frequente nas fábricas em geral. A segunda estratégia aproveita a possibilidade de desmembrar setores produtivos, comum em instalações de produção de combustível nuclear. Ambas as estratégias geraram diferentes cenários de produção, os quais devem ser seguros em relação à criticalidade. Foram coletados dados de uma fábrica real de combustível nuclear para reatores de pesquisa. As duas estratégias foram aplicadas a esses dados com a finalidade de testar o modelo proposto, o que configurou um estudo de caso. A aplicação das estratégias aos dados coletados deu-se por meio de simulação de eventos discretos em computador. Foram criados diversos modelos de simulação para abranger todos os cenários gerados, de forma que o teste indicou um aumento da capacidade produtiva de até 207% sem necessidade de aquisição de novos equipamentos. Os resultados comprovam que o modelo atingiu plenamente o objetivo proposto. Como principal conclusão pode-se apontar a eficácia do modelo proposto, fato que foi validado pelos dados da fábrica.<br>Although many nuclear fuel factories have small production volumes, the demand for nuclear fuel for research reactors is increasing worldwide. This work established a conceptual model with two strategies to increase the production capacity of these factories. We addressed factories that produce plate-type fuel elements loaded with LEU U3Si2-Al, which are typically used in nuclear research reactors. The first strategy is based on production management literature and is a regular practice in general manufacturing plants. The second strategy takes advantage of the fact that productive sectors can be separated in nuclear fuel production facilities. Both strategies have generated different production scenarios that are assumed to be safe in relation to nuclear criticality. We collected data from a real plant that produces nuclear fuel for research reactors and applied the model to that data, aiming to test the proposed model by setting up a case study. Through the use of computer software, we applied the two strategies to this data by means of discrete events simulation and created several simulation models in order to cover all generated scenarios. Our tests indicated an increase of up to 207% in productive capacity without the need of acquiring new equipment, thus showing that the model has fully achieved its proposed objective. One of the main conclusions that we point out is the models effectiveness, which was validated by the factory data.

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PORTO, PETERSON. "Otimização da análise isotópica de UF sub(6) utilizando-se a técnica de espectrometria de massas por quadrupolo." reponame:Repositório Institucional do IPEN, 2006. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11468.

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21

Vorster, Schalk Willem. "Corrosion behaviour of copper alloys in gaseous uranium hexafluoride." Thesis, 2015. http://hdl.handle.net/10539/18627.

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22

Sowden, Miles. "Quantitative mass spectrometric determination of trace impurities in uranium hexafluoride using relative response factors." Diss., 1993. http://hdl.handle.net/2263/32781.

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A method has been developed that uses uranium hexafluoride as the internal standard to quantitatively determine trace impurities in the uranium hexafluoride using relative response factors. A computer program was written to control the mass spectrometer and determine the concentrations of target impurities present. Overlapping spectra are deconvoluted using the Gauss-Seidel iterative method. The composition of the sample is determined by comparing the peak height ratios of the target impurities to the internal standard. Measurement parameters are easily modified using the menu driven program. A flexible database allows the list of target impurities to be extended to accommodate any changes in analytical requirements. The method has been adapted for automatic on-line measurements. The technique was evaluated by analysing a number of carefully prepared standards. Nine target impurities were studied which ranged in concentration from parts per million to percentages. An overall precision of fifteen percent was obtained.<br>Dissertation (MSc)--University of Pretoria, 1993.<br>gm2013<br>Chemistry<br>unrestricted

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