Aquifers are an important storage location and source of fresh groundwater. They may become polluted by a number of contaminants including mobile divalent radionuclides such as strontium-90 which is a byproduct of uranium fission. A method for remediating such divalent radionuclides is sequestration through co-precipitation into calcium carbonate. Calcium carbonate precipitation occurs naturally but can be enhanced by the use of ureolytic microorganisms living within the aquifer. The microbial enzyme urease cleaves ammonia from urea (added as a stimulant to the aquifer) increasing the pH and subsequently pushing the bicarbonate equilibrium towards precipitation. Laboratory experimentation is necessary to better predict field scale outcomes of remediation that is driven by ureolytic calcium carbonate co-precipitation. To aid in such laboratory experiments, I constructed two ureolytic organisms which contain green fluorescent protein (GFP) so that the location of the microbes in relation to media flow paths and precipitation can be viewed by microscopy in a 2- dimensional porous medium flow cell reactor. The reactor was operated with a parallel flow regime where the two influent media would not promote microbially induced calcium carbonate precipitation until they were mixed in the flow cell. A demonstration study compared the results of parallel flow and mixing in the reactor operated with and without one of the GFP-containing ureolytic organisms. The growth and precipitation of calcium carbonate within the reactor pore space altered flow paths to promote a wider mixing zone and a more widely distributed overall calcium carbonate precipitation pattern. This study will allow optimization of remediation efforts of contaminants such as strontium-90 in aquifers. / Graduation date: 2012

La dissolution de verres borosilicatés en présence de minéraux magnésiens a été étudiée. Ces minéraux (dolomite, illite, smectite…) appartiennent à la couche géologique (Callovo-Oxfordien) destinée à accueillir le stockage des déchets nucléaires vitrifiés en France. Ils contiennent du magnésium, élément capable d'entretenir l'altération du verre lorsqu'il est disponible en solution. Dans les milieux confinés du stockage, la réactivité des solides contrôle la composition de la solution et peut être la force motrice de l'altération des verres nucléaires. Les expériences montrent que les carbonates magnésiens (hydromagnésite, dolomite) entretiennent l'altération du verre : la précipitation de silicates de magnésium empêche la recondensation du silicium dans la couche passivante en surface du verre. Plus le minéral magnésien est soluble, plus l'altération du verre est importante. Les phases argileuses purifiées (illite, smectite…) du Callovo-Oxfordien (COx) augmentent également l'altération du verre. La moitié du magnésium échangeable de ces phases a été remplacée par du sodium lors du protocole de purification. Dans ces conditions, l'effet des phases argileuses sur l'altération du verre est en partie dû au pH acide qu'elles imposent. Le modèle d'altération des verres GRAAL implémenté dans le code de transport réactif HYTEC a permis de confirmer et de quantifier les mécanismes identifiés à partir des expériences en système fermé. Des expériences en cellule de diffusion, deux compartiments séparés par une barrière diffusive inerte, ont permis de valider une modélisation du transport réactif. Ces expériences, plus représentatives des conditions de stockage, où le bloc de verre sera séparé du COx par les produits de corrosion des aciers, illustrent le ralentissement des cinétiques attendu compte tenu de l'éloignement du verre et des minéraux réactifs. / Borosilicate glasses dissolution has been studied in presence of magnesium minerals. Those minerals (dolomite, illite, smectite…) belong to the Callovo-Oxfordian (COx) claystone layer, studied in France as a potential site for nuclear waste disposal. Such minerals contain magnesium, an element able to sustain glass alteration when it is available in solution. In the confined media of the wastes disposal, thesolids reactivity controls the solution composition and can be the driving force of nuclear glass alteration. Experiments show that magnesium carbonates (hydromagnesite and dolomite) increase in the glass alteration: the precipitation of magnesium silicates consumes silicon which slows down the formation of the glass passivating layer. The lower the magnesium mineral solubility, the lower the glass alteration.The purified clay phases (illite, smectite…) from the COx layer increase the glass alteration. Half the magnesium was remplaced by sodium during the purification process. In such conditions, the effect of clay phases on glass alteration is in part due to the acidic pH-buffering effect of the clay fraction. The GRAAL model implemented in the geochemical transport code HYTEC has confirmed and quantified the mechanisms put in evidence in the experiments. Cells diffusion experiments where the two solids were separated by an inert diffusion barrier allow to valid reactive transport modelling. Such experiments are more representative of the glass package which will be separated from the COx by corrosion products. They show that glass alteration rate is reduced when solids are not close.

Em cumprimento às normas que regulam a transferência e deposição final de rejeitos radioativos, o inventário de radionuclídeos de cada embalado contendo tais rejeitos deve ser estimado e declarado. Os limites autorizados são definidos em função das doses de radiação que indivíduos do público podem vir a receber anualmente a partir do repositório. Tais limites se referem principalmente às concentrações de atividade, dadas em Bq/g, dos radionuclídeos presentes nos embalados com rejeitos. A grande maioria dos radionuclídeos emissores de raios-gama pode ter a respectiva concentração de atividade determinada diretamente por medidas externas aos embalados. Entretanto, determinação análoga para os radionuclídeos emissores exclusivos de partículas alfa ou beta, bem como de alguns emissores de raios-gama e/ou raios-X cuja energia, intensidade absoluta de emissão e/ou atividade são muito baixas denominados genericamente Radionuclídeos de Difícil Medição (RDMs) requer procedimentos radioquímicos complexos para isolar a espécie química de interesse dos interferentes presentes nas matrizes de rejeitos. Ademais, nesse caso é necessário coletar amostras de cada embalado, acarretando elevadas doses de radiação para os operadores e altos custos logísticos, decorrentes do grande número de embalados com rejeitos radioativos que necessitam de caracterização em uma instalação nuclear. Uma metodologia alternativa para abordar esse problema consiste em obter correlações empíricas entre alguns radionuclídeos possíveis de serem medidos diretamente, como 60Co e 137Cs denominados Radionuclídeos Chave (RCs) e os RDMs. Essa metodologia, denominada Fator de Escala, foi aplicada no presente trabalho com a finalidade de determinar tais correlações, na forma de Fatores de Escala ou Funções de Correlação, para os principais rejeitos de baixa e média atividades do reator nuclear de pesquisa IEA-R1. / Regulations regarding transfer and final disposal of radioactive waste require that the inventory of radionuclides for each container enclosing such waste must be estimated and declared. The regulatory limits are established as a function of the annual radiation doses that members of the public could be exposed to from the radioactive waste repository, which mainly depend on the activity concentration of radionuclides, given in Bq/g, found in each waste container. Most of the radionuclides that emit gamma-rays can have their activity concentrations determined straightforwardly by measurements carried out externally to the containers. However, radionuclides that emit exclusively alpha or beta particles, as well as gamma-rays or X-rays with low energy and low absolute emission intensity, or whose activity is very low among the radioactive waste, are generically designated as Difficult to Measure Nuclides (DTMs). The activity concentrations of these DTMs are determined by means of complex radiochemical procedures that involve isolating the chemical species being studied from the interference in the waste matrix. Moreover, samples must be collected from each container in order to perform the analyses inherent to the radiochemical procedures, which exposes operators to high levels of radiation and is very costly because of the large number of radioactive waste containers that need to be characterized at a nuclear facility. An alternative methodology to approach this problem consists in obtaining empirical correlations between some radionuclides that can be measured directly such as 60Co and 137Cs, therefore designated as Key Nuclides (KNs) and the DTMs. This methodology, denominated Scaling Factor, was applied in the scope of the present work in order to obtain Scaling Factors or Correlation Functions for the most important radioactive wastes with low and intermediate-activity level from the IEA-R1 nuclear research reactor.

Em cumprimento às normas que regulam a transferência e deposição final de rejeitos radioativos, o inventário de radionuclídeos de cada embalado contendo tais rejeitos deve ser estimado e declarado. Os limites autorizados são definidos em função das doses de radiação que indivíduos do público podem vir a receber anualmente a partir do repositório. Tais limites se referem principalmente às concentrações de atividade, dadas em Bq/g, dos radionuclídeos presentes nos embalados com rejeitos. A grande maioria dos radionuclídeos emissores de raios-gama pode ter a respectiva concentração de atividade determinada diretamente por medidas externas aos embalados. Entretanto, determinação análoga para os radionuclídeos emissores exclusivos de partículas alfa ou beta, bem como de alguns emissores de raios-gama e/ou raios-X cuja energia, intensidade absoluta de emissão e/ou atividade são muito baixas denominados genericamente Radionuclídeos de Difícil Medição (RDMs) requer procedimentos radioquímicos complexos para isolar a espécie química de interesse dos interferentes presentes nas matrizes de rejeitos. Ademais, nesse caso é necessário coletar amostras de cada embalado, acarretando elevadas doses de radiação para os operadores e altos custos logísticos, decorrentes do grande número de embalados com rejeitos radioativos que necessitam de caracterização em uma instalação nuclear. Uma metodologia alternativa para abordar esse problema consiste em obter correlações empíricas entre alguns radionuclídeos possíveis de serem medidos diretamente, como 60Co e 137Cs denominados Radionuclídeos Chave (RCs) e os RDMs. Essa metodologia, denominada Fator de Escala, foi aplicada no presente trabalho com a finalidade de determinar tais correlações, na forma de Fatores de Escala ou Funções de Correlação, para os principais rejeitos de baixa e média atividades do reator nuclear de pesquisa IEA-R1. / Regulations regarding transfer and final disposal of radioactive waste require that the inventory of radionuclides for each container enclosing such waste must be estimated and declared. The regulatory limits are established as a function of the annual radiation doses that members of the public could be exposed to from the radioactive waste repository, which mainly depend on the activity concentration of radionuclides, given in Bq/g, found in each waste container. Most of the radionuclides that emit gamma-rays can have their activity concentrations determined straightforwardly by measurements carried out externally to the containers. However, radionuclides that emit exclusively alpha or beta particles, as well as gamma-rays or X-rays with low energy and low absolute emission intensity, or whose activity is very low among the radioactive waste, are generically designated as Difficult to Measure Nuclides (DTMs). The activity concentrations of these DTMs are determined by means of complex radiochemical procedures that involve isolating the chemical species being studied from the interference in the waste matrix. Moreover, samples must be collected from each container in order to perform the analyses inherent to the radiochemical procedures, which exposes operators to high levels of radiation and is very costly because of the large number of radioactive waste containers that need to be characterized at a nuclear facility. An alternative methodology to approach this problem consists in obtaining empirical correlations between some radionuclides that can be measured directly such as 60Co and 137Cs, therefore designated as Key Nuclides (KNs) and the DTMs. This methodology, denominated Scaling Factor, was applied in the scope of the present work in order to obtain Scaling Factors or Correlation Functions for the most important radioactive wastes with low and intermediate-activity level from the IEA-R1 nuclear research reactor.

Le projet Cigéo, mené par l’ANDRA, vise à permettre à l’horizon 2030 le stockage géologique des déchets les plus radioactifs du parc nucléaire français. Ces déchets, qui seraient placés dans des alvéoles souterraines de plusieurs centaines de mètres, sont susceptibles de relâcher de l’hydrogène gazeux (H2), un gaz inflammable dans l’air lorsque sa concentration dépasse 4%. Pour la sécurité des installations, il est indispensable de s’assurer que la concentration de H2 dans les alvéoles de stockage reste inférieure à sa limite de dangerosité. L’objectif de cette thèse, menée à l’ONERA, est de concevoir et réaliser un Lidar permettant de profiler à distance la concentration de H2 (0-4%), sur plusieurs centaines de mètres, avec une forte résolution spatiale (< 3 m), et de proposer ainsi un moyen non intrusif de détection et de prévention du risque lié à l’hydrogène. Le principe retenu est celui d’un Lidar Raman vibrationnel dans le domaine ultra-violet (355 – 420 nm). Pour sa conception, nous avons pris en compte les conditions particulières prévues dans les alvéoles de stockage. Une chaine de détection très sensible à comptage de photons a été choisie et mise en oeuvre, basée sur des détecteurs SiPM (Silicium Photomultiplier). La nécessité d’employer une voie de mesure de la vapeur d’eau, simultanément à l’hydrogène, a été mise en évidence et est liée au recouvrement partiel des spectres de diffusion Raman de H2 et H2O. Un analyseur spectral à trois voies de mesure (H2, H2O, et N2 utilisé comme référence) a été conçu et mis en place. Une méthode de traitement de signal en temps réel a enfin été réalisée pour visualiser les profils de concentrations de H2 et H2O. L’ensemble du système lidar a pu être testé dans une scène de portée réduite (100 m) permettant des relâchements d’hydrogène. Des mesures simultanées de profils de vapeur d’eau naturelle et de dihydrogène (0-2%) ont pu être démontrées avec succès à 85 m, avec une résolution spatiale et temporelle de 1 mètre et 1 minute respectivement, pour une détectivité de 600 ppm. / The CIGEO project, led by the ANDRA agency, aims at enabling future deep geological disposal of french nuclear waste packages. Those packages could be stored in hundred-meters long underground galleries, and may release hydrogen gas (H2), which is explosive at concentrations above 4% in the air. For safety concerns, it is important to ensure that H2 concentration remains well below the lower explosive limit. The objective of this thesis work, conducted at the ONERA agency, is to design and build a lidar which enable high-resolution (3 m) remote profiling of H2 concentration (0-4%) over hundreds of meters. Such a lidar could perform nonintrusive H2 detection and then prevent H2-related explosion risks. This lidar measures vibrational Raman scattering in the UV domain (355 – 420 nm). Its design takes into account the specific conditions expected in storage galleries. A highspeed and sensitive detection stage has been chosen, based on SiPM (Silicium Photomultiplier) technology in photon counting mode. Due to a spectral overlap between molecular hydrogen and water vapor Raman spectra, the need of a H2O measurement channel has been demonstrated. A three-channel spectral analyzer (H2, H2O and N2 used as reference) has been designed and implemented. Signal processing in real time has been developed to display H2 and H2O concentration profiles. This lidar has been tested in a reduced range scene (100 m) enabling hydrogen gas releases. Simultaneous measurements of concentration profiles of natural water vapor and hydrogen gas (0-2%) have been performed at 85 m with 1-meter and 1-minute resolution and a 600 ppm detectivity.

The purpose of this research is to develop a methodology for a thorium fuel recycling analysis that provides results for isotopics and radio-toxicity evaluation and analysis. This research is motivated by the need to reduce the long term radiological hazard in spent nuclear fuel, which mitigates the mixing hazard (radiotoxicity and chemical toxicity) and decay heat load on the repository. The first part of the thesis presents comparison of several once-through cases with uranium and thorium fuels to show how transuranics build up as fuel is depleted. The once-through analysis is performed for the following pairs of comparison cases: low enriched uranium dioxide (UOX) vs. thorium dioxide with 233UOX (233U-ThOX), natural uranium dioxide mixed with transuranic oxides (U-TRUOX) vs. thorium dioxide mixed with transuranic oxides (Th-TRUOX), natural uranium dioxide mixed with weapons grade plutonium dioxide (U-WGPuOX) vs. thorium dioxide mixed with weapons grade plutonium dioxide (Th-WGPuOX), natural uranium dioxide mixed with reactor grade plutonium dioxide (U-RGPuOX) vs. thorium mixed with reactor grade plutonium dioxide (Th-RGPuOX). The second part of the research evaluates the thorium fuel equilibrium cycle in a pressurized water reactor (PWR) and compares several recycling cases with different partitioning schemes. Radio-toxicity results of the once-through cycle and multi-recycle calculations demonstrate advantages for thorium fuel and reprocessing with respect to long term nuclear waste management.

No description available.

Thesis (Ph. D.)--University of Missouri-Columbia, 1997. / Typescript. Vita. Includes bibliographical references. Also available on the Internet.

Thesis (Ph. D.)--University of Missouri-Columbia, 1997. / Typescript. Vita. Includes bibliographical references. Also available on the Internet.

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