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Dissertations / Theses on the topic 'Radiolysis of uranium hexafluoride'

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Published: 5 June 2025

Last updated: 2 August 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 hexafl

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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

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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4

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

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5

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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6

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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7

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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8

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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9

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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10

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 réac

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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

Odorowski, Mélina. "Etude de l'altération de la matrice (U,Pu)O2 du combustible irradiéen conditions de stockage géologique : Approche expérimentale et modélisation géochimique." Thesis, Paris, ENMP, 2015. http://www.theses.fr/2015ENMP0057/document.

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Afin d’évaluer les performances du combustible irradié en situation de stockage géologique, des recherches sont menées sur le comportement à long terme des combustibles irradiés (UOx et MOx) en conditions environnementales se rapprochant de celles du site de stockage français. L’objectif de cette thèse est de déterminer si la géochimie de la couche géologique d'argilites du Callovo-Oxfordien (COx) et la corrosion des conteneurs en acier (produisant du fer et de l'hydrogène) ont un impact sur la dissolution oxydante de la matrice (U,Pu)O2 sous radiolyse alpha de l’eau.Des expériences de lixivia

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15

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 tip

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16

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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17

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

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18

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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Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2014-11-10T12:03:00Z No. of bitstreams: 0<br>Made available in DSpace on 2014-11-10T12:03:00Z (GMT). No. of bitstreams: 0<br>Tese (Doutorado em Tecnologia Nuclear)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

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19

Barreiro, Fidalgo Alexandre. "Experimental studies of radiation-induced dissolution of UO2 : The effect of intrinsic solid phase properties and external factors." Doctoral thesis, KTH, Tillämpad fysikalisk kemi, 2017. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-205605.

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Dissolution of the UO2 matrix is one of the potential routes for radionuclide release in a future deep geological repository for spent nuclear fuel. This doctoral thesis focuses on interfacial reactions of relevance in radiation-induced dissolution of UO2 and is divided in two parts: In the first part, we sought to explore the effects of solid phase composition: The impact of surface stoichiometry on the reactivity of UO2 towards aqueous radiolytic oxidants was studied. H2O2 reacts substantially faster with stoichiometric UO2 than with hyperstoichiometric UO2. In addition, the release of urani

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20

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 aprove

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21

Odorowski, Mélina. "Etude de l'altération de la matrice (U,Pu)O2 du combustible irradiéen conditions de stockage géologique : Approche expérimentale et modélisation géochimique." Electronic Thesis or Diss., Paris, ENMP, 2015. http://www.theses.fr/2015ENMP0057.

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Afin d’évaluer les performances du combustible irradié en situation de stockage géologique, des recherches sont menées sur le comportement à long terme des combustibles irradiés (UOx et MOx) en conditions environnementales se rapprochant de celles du site de stockage français. L’objectif de cette thèse est de déterminer si la géochimie de la couche géologique d'argilites du Callovo-Oxfordien (COx) et la corrosion des conteneurs en acier (produisant du fer et de l'hydrogène) ont un impact sur la dissolution oxydante de la matrice (U,Pu)O2 sous radiolyse alpha de l’eau.Des expériences de lixivia

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22

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 e

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23

Kerleguer, Valentin. "Apport de l'étude de matériaux modèles U1-xPuxO2 à la compréhension des mécanismes d'altération des combustibles UOx et MOx en stockage géologique." Electronic Thesis or Diss., Université Paris sciences et lettres, 2020. http://www.theses.fr/2020UPSLM061.

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L’influence des conditions environnementales du stockage géologique sur la lixiviation de la matrice des combustibles UOx et MOx a été étudiée selon une complexification progressive : eau carbonatée, eau synthétique de l’argilite du Callovo-Oxfordien (COx), eau du Cox avec fer métal ou argilite. Deux matériaux modèles émetteurs alpha ont été sélectionnés : des pastilles de UO2 faiblement dopées en Pu et des pastilles homogènes de MOx U0.73Pu0.27O2. Les protocoles expérimentaux, spécifiquement développés, ne montrent pas un effet important de l’argilite sur l’altération de UO2. Le plutonium dim

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24

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

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25

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

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