Ce travail reprend les résultats d'une prospection sur les indices minéralisés du Dôme de la Mure. Il décrit succintement les indices minéralisés rencontrés dans le socle et la couverture sédimentaire. Ceci de Laffrey jusqu'à Mens .

La consommation d'aliments riches en ellagitannins (ETs) pourrait être associée principalement à la prévention des maladies cardiovasculaires et la régulation des cancers hormono-dépendants. Néanmoins, les ETs ne sont pas biodisponibles en tant que tel et, après avoir été partiellement transformés en acide ellagique (EA) dans le tractus gastro-intestinal (GI) supérieur, ils sont métabolisés dans le côlon par la flore intestinale en urolithines, un groupe de molécules plus biodisponibles et bioactives qui peuvent persister jusqu'à 4 jours à des concentrations relativement élevées dans le plasma et l'urine. La variabilité de l'excrétion des urolithines dans l'urine est importante et à partir d'un échantillon de population de 26 volontaires sains, trois groupes principaux d'individus ont pu être distingués : "faible ou non-excréteur d'urolithin », « Excréteur prédominant d'UA et dérivés» et « Excréteur prédominant d'UB et dérivés»". Ces groupes ont également été observés en considérant la cinétique totale d'excrétion sur une période de 4 jours après ingestion du jus et à des périodes différentes tout au long d'une année. Bien que les variabilités inter-et intra-individuelles soient relativement élevées, les individus conservent leur statut au cours des différentes périodes d'intervention même en modifiant les quantités d'ETs ingérées. L'analyse par UPLC-PDA/ESI-Q-TOF/MS2 a permis d'attribuer hypothétiquement une identité à 15 autres métabolites d'ETs dans l'urine, mais le profilage métabolomique n'a pas permis de discriminer d'autres composés exceptés les dérivés d'UA ou d'UB. La fermentation in-vitro des ETs et EA, par les matières fécales a montré une voie métabolique spécifique qui débouche sur la production d'UA. Néanmoins, les métabolites excrétés in vivo sont beaucoup plus complexes ce qui met en évidence de fortes interactions entre le système excréteur de l'hôte et la composition du microbiote intestinal. La recirculation hépatique suivie par une re-conversion des métabolites de phase II dans le côlon permettrait d'expliquer l'excrétion d'UB chez certains volontaires. L'écologie spécifique de la flore intestinale évaluée par la méthode des empreintes PCR-DGGE a permis d'identifier quelques microorganismes associés à une plus grande capacité de bioconversion des ETs en urolithins / Consumption of dietary ellagitannins (ETs) could be associated mainly with prevention of cardiovascular diseases and regulation of hormone-dependent cancers. Nonetheless, ETs are not bioavailable as such; therefore, after being partially converted into ellagic acid (EA) in the upper gastrointestinal (GI) tract, they undergo sequential bioconversion in the colon by gut microbiota into urolithins, a more bioavailable and bioactive group of molecules that persist up to 4 days at relatively high concentrations in urine. Variability of urolithin excretion in urine is high and three main groups, “no or low urolithin excreters,” “predominantly UA derivatives excreters” and “predominantly UB derivatives excreters,” were observed on a cohort of 26 healthy volunteers. These categories were also unambiguously observed following the total excretion of main ETs' metabolites over a 4 day period after ingesting one shot of juice, and at different periods of time along one year. Although relatively high inter- and intra-individual variabilities were observed, individuals preserved their status during various intervention periods with different amounts of ETs ingested. UPLC-PDA and ESI-Q-TOF/MS1 and MS2 allowed the tentative assignment of an identity to 15 other ETs metabolites in urine, but this profiling did not allow the discrimination of any other compounds aside from UA or UB derivatives. In-vitro fermentation of ETs and EA with fecal stools showed a specific metabolic pathway ending in the production of UA. Nonetheless, metabolites excreted in-vivo are much more complex, highlighting strong interactions between host excretory system and composition of gut microbiota. Hepatic recirculation and additional bioconversion of Phase II metabolites in the colon may explain predominant excretion of UB in some volunteers. Microbiota ecology assessed by PCR-Denaturing Gradient Gel Electrophoresis (DGGE) fingerprint method allowed the association of some microorganism species to higher capacity of bioconversion of dietary ETs into urolithins.Key words: Ellagitannins, blackberry, urolithin, colonic metabolites, ETs degradation patterns, gut microbiota, gastrointestinal tract,

Orientador: Edgar Salvadori De Decca / Tese (doutorado) - Universidade Estadual de Campinas, Instituto de Filosofia e Ciencias Humanas / Made available in DSpace on 2018-07-31T22:55:24Z (GMT). No. of bitstreams: 1 Gallo_IvoneCeciliad'Avila_D.pdf: 17430302 bytes, checksum: c5d8c33ad605f3c121b4dfa8fdd25b26 (MD5) Previous issue date: 2002 / Resumo: Na França do século XIX, nasciam um movimento de idéias e um movimento social dotados de novas características. Os pensadores sociais, Saint Simon, Charles Fourier e Cabet introduziam, corno matéria para a reflexão, os problemas sociais, evidenciados por um movimento social que contestava o modelo econômico e político fundado no sistema industrial. O surgimento de uma preocupação com a indigência, o desemprego, a opressão da mulher e da criança, a exploração do trabalhio, bem como a proposição de soluções a estes problemas, foram as contribuições legadas por estes pensadores e que, por outro lado, retomaram para a sociedade, imprimindo ao nascente movimento operário uma marca forte. A idéia de transformar o mundo a partir do estabelecimento de falanstérios, de acordo com os princípios de Charles Fourier, apossara-se de parte do movimento operário e, em pouco tempo, assistia-se à emigração de operários franceses rumo às Américas, com o fim de implantar colônias societárias. O assunto desta tese é o movimento fourierista na França e a fundação de um falanstério no Saí (SC), em 1840, como primeira experiência das idéias de Fourier realizada fora do continente europeu. Deste ensaio teria brotado, no Rio de Janeiro, um movimento fourierista brasileiro, ainda que de pouco alcance / Abstract: In nineteenth-century France, a current of ideas and a social movement bearing new features were bom. Social theorists, such as Saint-Simon, Charles Fourier and Etienne Cabet, introduced as matter for reflection social problems, brought to evidence by a social movement, which contested the economic and polítical model founded in the industrial system. The rising of concern with the outcasts, unemployment, oppression on women and children, labor exploitation, but also with the proposal of solutions for these problems were the contributions legated by these social theorists, that in the other hand, returned to society, establishing a strong brand on the early labor movement. The idea of world transformation through the establishment of phalansteries, according to the principles of Charles Fourier, gained a part of the labor movement, and, shortly afier, French workers emigrated to the Americas, with the aim of creating societarian colonies. The subject of this thesis is the Fourierist movement in France and the foundation in 1840 of a phalanstery at Saí (Province of Santa Catarina, southern Brazil), as the first experiment of Fourier's ideas out of continental Europe. Out of this essay rose, at Rio de Janeiro, a Brazilian Fourierist movement, that nevertheless attained a limited influence / Doutorado / Doutor em História

Dans le contexte d'un déploiement massif du nucléaire civil au niveau mondial, le problème de l'approvisionnement en U-235 se posera à des échéances humaines. L'industrie nucléaire d'aujourd'hui, sous-génératrice, serait, dans un tel cas de figure, inapte à satisfaire les besoins énergétiques du monde de façon durable. La transition vers des filières iso ou surgénératrices, qui optimisent l'utilisation de la matière fissile, est alors pertinente. Parmi les technologies qui permettent une telle optimisation, le cycle du thorium, Th/U-233 utilisé en spectre de neutrons thermique, est doublement intéressant; il permettrait, dans des concepts de type réacteur à sels fondus thermique, l'isogénération de la matière fissile tout en nécessitant de faibles inventaires initiaux en U-233. La production de cette quantité d'U-233, nécessaire au démarrage de la filière, peut être produite en amont, dans des réacteurs d'aujourd'hui (à eau sous pression), utilisant un combustible de type mixte oxyde thorium-plutonium. <br /><br />Ce travail concerne d'une part le développement d'outils de calcul nécessaires à l'étude neutronique, par simulation Monte Carlo (M.C), des réacteurs nucléaires et de leur combustible. Qu'ils soient de génération future ou de technologie actuelle utilisant un combustible innovant, la simulation des réacteurs par les méthodes M.C. est particulièrement bien adaptée car elle ne repose que sur la connaissance des données nucléaires, et peut traiter des géométries complexes et exactes en effectuant le transport des neutrons à énergie continue. <br /><br /><br />Le code MURE, qui encapsule le code de transport validé et reconnu MCNP, a été écrit pour simuler l'évolution du combustible sous irradiation. C'est un code modulaire, écrit en C++, qui permet, entre autres, de simuler des évolutions à puissance et à réactivité constantes. <br /><br /><br />Dans un deuxième temps, nous avons entrepris l'étude du combustible MOX ThPu en REP en vue de détérminer des teneurs en plutonium satisfaisant les critères de sûreté et avons quantifié la production d'uranium-233 en fin de combustion. Ceci nous permet de considèrer et de valider différents scénarios de transition du parc français vers un parc de réacteurs isogénérateurs utilisant le cycle du thorium, où l'U-233, aura été produit dans des réacteurs à eau sous pression utilisant du MOX thorié.

Conselho Nacional de Pesquisa e Desenvolvimento Científico e Tecnológico - CNPq / This research intends to analyze the actions undertaken by the intellectual, homoeopathic and utopian socialist, Benoît Jules Mure (1809-1858), for the dissemination of the Method of Universal Teaching while he was in Brazil, bearing in mind that this Method presupposes equality between human intelligences and which was discovered by the French pedagogue Jean-Joseph Jacotot (1770-1840) in the year 1818 gaining notoriety in several regions of Europe, one can see its circulation also in nineteenth-century Brazil. The time frame used here is justified, therefore, it comprises the period of 1840, the year in which Mure landed in the country, in 1848, the date on which it left, and marks its passage in Brazilian lands. It is worth mentioning that this research is based on the presuppositions of the History of Education, in the perspective of Cultural History. The research uses as sources, non-pedagogical periodicals that circulated in the province of Rio de Janeiro during the period. Especially the Jornal do Commercio of Rio de Janeiro, founded in 1827 and also A Sciencia: Synthetica Magazine of Human Knowledge, a production of Mure himself and his group of adepts with periodical publication from 1847 to 1848. The sources worked here were found in archives online from the National Library of Brazil. It is noteworthy that Benoît Mure acted in different ways in favor of the dissemination of Universal Teaching, from publications about the Method, to its application in the Homeopathic School of Brazil. We hope that this analysis represents an important contribution to the historical knowledge of the Method of Universal Teaching in Brazil, making possible the broadening of the field of Education History, since it is an unexplored subject in Brazilian educational historiography. / Esta pesquisa analisa as ações empreendidas pelo intelectual, médico homeopata e socialista utópico, Benoît Jules Mure (1809-1858), na divulgação do Método do Ensino Universal, enquanto esteve no Brasil, tendo presente que tal Método defende a igualdade entre as inteligências humanas e, que foi descoberto pelo pedagogo francês Jean-Joseph Jacotot (1770-1840) no ano de 1818 ganhando notoriedade em diversas regiões da Europa; percebe-se sua circulação também no Brasil do século XIX, através da atuação do intelectual. O marco temporal aqui utilizado justifica-se, pois, compreende o período de 1840, ano em que Mure desembarcou no país à 1848, data em que foi embora e, marca sua passagem em terras brasileiras. Vale destacar que esta investigação encontra-se alicerçada nos pressupostas da História da Educação, na perspectiva da História Cultural. A pesquisa utiliza como fontes, periódicos não pedagógicos que circularam na província do Rio de Janeiro durante a época. Especialmente o Jornal do Commercio do Rio de Janeiro, fundado em 1827 e, também A Sciencia: Revista Synthetica dos Conhecimentos Humanos, uma produção do próprio Mure e seu grupo de adeptos com publicação periódica de 1847 a 1848. As fontes aqui trabalhadas foram encontradas nos arquivos online da Biblioteca Nacional do Brasil. Destaca-se que Benoît Mure atuou de diferentes formas a favor da divulgação do Ensino Universal, desde publicações sobre o Método, até a sua aplicação na Escola Homeopathica do Brasil. Esperamos que essa análise represente uma contribuição importante quanto ao conhecimento histórico do Método do Ensino Universal no Brasil, possibilitando o alargamento do campo da História da Educação, já que trata-se de um assunto, por enquanto, inexplorado na historiografia educacional brasileira. / São Cristóvão, SE

Le code MURE est basé sur le couplage d’un code Monte Carlo statique et le calcul de l’évolution pendant l’irradiation et les différentes périodes du cycle (refroidissement, fabrication). Le code MURE est ici utilisé pour analyser deux différentes questions : le mono-recyclage de l’Am dans les réacteurs français de type REP et la conversion du coeur du MNSR (Miniature Neutron Source Reactor) au Ghana d’un combustible à uranium hautement enrichi (HEU) vers un combustible faiblement enrichi (LEU), dans le cadre de la lutte contre la prolifération. Dans les deux cas, une comparaison détaillée est menée sur les taux d’irradiation et les radiotoxicités induites (combustibles usés, déchets).Le combustible UOX envisagé est enrichi de telle sorte qu’il atteigne un taux d’irradiation de 46 GWj/t et 68 GWj/t. Le combustible UOX usé est retraité, et le retraitement standard consiste à séparer le plutonium afin de fabriquer un combustible MOX sur base d’uranium appauvri. La concentration du Pu dans le MOX est déterminée pour atteindre un taux d’irradiation du MOX de 46 et 68 GWj/t. L’impact du temps de refroidissement de l’UOX usé est étudié (5 à 30 ans), afin de quantifier l’impact de la disparition du 241PU (fissile) par décroissance radioactive (T=14,3 ans). Un refroidissement de 30 ans demande à augmenter la teneur en Pu dans le MOX. L’241Am, avec une durée de vie de 432 ans, jour un rôle important dans le dimensionnement du site de stockage des déchets vitrifiés et dans leur radiotoxicité à long terme. Il est le candidat principal à la transmutation, et nous envisageons donc son recyclage dans le MOX, avec le plutonium. Cette stratégie permet de minimiser la puissance résiduelle et la radiotoxicité des verres, en laissant l’Am disponible dans les MOX usés pour une transmutation éventuelle future dans les réacteurs rapides. Nous avons étudié l’impact neutronique d’un tel recyclage. Le temps de refroidissement de l’UOX est encore plus sensible ici car l’241Am recyclé est un fort poison neutronique qui dégrade les performances du combustible (taux d’irradiation, coefficients de vide et de température). Néanmoins, à l’exception de quelques configurations, le recyclage de l’Am ne dégrade pas les coefficients de sûreté de base. Le réacteur MNSR du Ghana fonctionne aujourd’hui avec de l’uranium enrichi à 90,2% (HEU), et nous étudions ici la possibilité de le faire fonctionner avec de l’uranium enrichi à 12,5%, en passant d’un combustible sur base d’aluminium à un oxyde. Les simulations ont été menées avec le code MURE, et montrent que le coeur LEU peut-être irradié plus longtemps, mais demande d’intervenir plus tôt sur le pilotage en jouant sur la quantité de béryllium en coeur. Les flux de neutrons dans les canaux d’irradiation sont similaires pour les coeurs HEU et LEU, de même pour les coefficients de vide. Le combustible LEU usé présente cependant une radiotoxicité et une chaleur résiduelle plus élevée, du fait de la production plus importante de transuraniens pendant l’irradiation. / The MURE code is based on the coupling of a Monte Carlo static code and the calculation of the evolution of the fuel during irradiation and cooling periods. The MURE code has been used to analyse two different questions, concerning the mono-recycling of Am in present French Pressurized Water Reactor, and the conversion of high enriched uranium (HEU) used in the Miniature Neutron Source Reactor in Ghana into low enriched uranium (LEU) due to proliferation resistance issues. In both cases, a detailed comparison is made on burnup and the induced radiotoxicity of waste or spent fuel. The UOX fuel assembly, as in the open cycle system, was designed to reach a burn-up of 46GWd/T and 68GWd/T. The spent UOX was reprocessed to fabricate MOX assemblies, by the extraction of Plutonium and addition of depleted Uranium to reach burn-ups of 46GWd/T and 68GWd/T, taking into account various cooling times of the spent UOX assembly in the repository. The effect of cooling time on burnup and radiotoxicity was then ascertained. Spent UOX fuel, after 30 years of cooling in the repository required higher concentration of Pu to be reprocessed into a MOX fuel due to the decay of Pu-241. Americium, with a mean half-life of 432 years, has high radiotoxic level, high mid-term residual heat and a precursor for other long lived isotope. An innovative strategy consists of reprocessing not only the plutonium from the UOX spent fuel but also the americium isotopes which dominate the radiotoxicity of present waste. The mono-recycling of Am is not a definitive solution because the once-through MOX cycle transmutation of Am in a PWR is not enough to destroy all the Am. The main objective is to propose a “waiting strategy” for both Am and Pu in the spent fuel so that they can be made available for further transmutation strategies. The MOXAm (MOX and Americium isotopes) fuel was fabricated to see the effect of americium in MOX fuel on the burn-up, neutronic behavior and on radiotoxicity. The MOXAm fuel showed relatively good indicators both on burnup and on radiotoxicity. A 68GWd/T MOX assembly produced from a reprocessed spent 46GWd/T UOX assembly showed a decrease in radiotoxicity as compared to the open cycle. All fuel types understudy in the PWR cycle showed good safety inherent feature with the exception of the some MOXAm assemblies which have a positive void coefficient in specific configurations, which could not be consistent with safety features. The core lifetimes of the current operating 90.2% HEU UAl fuel and the proposed 12.5% LEU UOX fuel of the MNSR were investigated using MURE code. Even though LEU core has a longer core life due to its higher core loading and low rate of uranium consumption, the LEU core will have it first beryllium top up to compensate for reactivity at earlier time than the HEU core. The HEU and LEU cores of the MNSR exhibited similar neutron fluxes in irradiation channels, negative feedback of temperature and void coefficients, but the LEU is more radiotoxic after fission product decay due to higher actinides presence at the end of its core lifetime.

The MURE code is based on the coupling of a Monte Carlo static code and the calculation of the evolution of the fuel during irradiation and cooling periods. The MURE code has been used to analyse two different questions, concerning the mono-recycling of Am in present French Pressurized Water Reactor, and the conversion of high enriched uranium (HEU) used in the Miniature Neutron Source Reactor in Ghana into low enriched uranium (LEU) due to proliferation resistance issues. In both cases, a detailed comparison is made on burnup and the induced radiotoxicity of waste or spent fuel. The UOX fuel assembly, as in the open cycle system, was designed to reach a burn-up of 46GWd/T and 68GWd/T. The spent UOX was reprocessed to fabricate MOX assemblies, by the extraction of Plutonium and addition of depleted Uranium to reach burn-ups of 46GWd/T and 68GWd/T, taking into account various cooling times of the spent UOX assembly in the repository. The effect of cooling time on burnup and radiotoxicity was then ascertained. Spent UOX fuel, after 30 years of cooling in the repository required higher concentration of Pu to be reprocessed into a MOX fuel due to the decay of Pu-241. Americium, with a mean half-life of 432 years, has high radiotoxic level, high mid-term residual heat and a precursor for other long lived isotope. An innovative strategy consists of reprocessing not only the plutonium from the UOX spent fuel but also the americium isotopes which dominate the radiotoxicity of present waste. The mono-recycling of Am is not a definitive solution because the once-through MOX cycle transmutation of Am in a PWR is not enough to destroy all the Am. The main objective is to propose a "waiting strategy" for both Am and Pu in the spent fuel so that they can be made available for further transmutation strategies. The MOXAm (MOX and Americium isotopes) fuel was fabricated to see the effect of americium in MOX fuel on the burn-up, neutronic behavior and on radiotoxicity. The MOXAm fuel showed relatively good indicators both on burnup and on radiotoxicity. A 68GWd/T MOX assembly produced from a reprocessed spent 46GWd/T UOX assembly showed a decrease in radiotoxicity as compared to the open cycle. All fuel types understudy in the PWR cycle showed good safety inherent feature with the exception of the some MOXAm assemblies which have a positive void coefficient in specific configurations, which could not be consistent with safety features. The core lifetimes of the current operating 90.2% HEU UAl fuel and the proposed 12.5% LEU UOX fuel of the MNSR were investigated using MURE code. Even though LEU core has a longer core life due to its higher core loading and low rate of uranium consumption, the LEU core will have it first beryllium top up to compensate for reactivity at earlier time than the HEU core. The HEU and LEU cores of the MNSR exhibited similar neutron fluxes in irradiation channels, negative feedback of temperature and void coefficients, but the LEU is more radiotoxic after fission product decay due to higher actinides presence at the end of its core lifetime.