Dissertations / Theses: 'Radioactive waste disposal in rivers'

1

Norris, James 1953. "Preliminary hydraulic characterization of a fractured schist aquifer at the Koongarra uranium deposit, Northern Territory, Australia." Thesis, The University of Arizona, 1989. http://hdl.handle.net/10150/291720.

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The Koongarra uranium deposit is hosted by quartz-chlorite schists. A conceptual model for the hydrogeology of the deposit is proposed on the basis of lithologic criteria and limited hydraulic testing. Water-level and aquifer-test data are presented that indicate the deposit lies within a partially confined, heterogeneous, anisotropic fractured-rock aquifer. The aquifer is dynamic with annual, diurnal, and semidiurnal water-level fluctuations. The results of aquifer tests indicate a high degree of connectivity in the aquifer. Fracture-dominated flow is observed in some tests, but the overall aquifer response appears to be that of an equivalent porous medium. A homogeneous, anisotropic model is used to estimate the transmissivity tensor for subregions of the aquifer. Anisotropy is well-developed with north- to east-northeast-oriented principal transmissivities. Northeast directions represent large-scale drawdown patterns and are subparallel to bedrock structure and the Koongarra fault. Northerly directions are localized and may reflect a less extensive fracture fabric or a flexure in the bedrock foliation.

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2

Trone, Paul M. "Textural and mineralogical characteristics of altered Grande Ronde basalt, northeastern Oregon : a natural analog for a nuclear waste repository in basalt." PDXScholar, 1987. https://pdxscholar.library.pdx.edu/open_access_etds/3824.

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Altered flows that are low-MgO chemical types of the Grande Ronde Basalt crop out in the steep walls of the Grande Ronde River canyon near Troy, Wallowa County, Oregon. The alteration effects in these flows are being investigated as a natural analog system to a high level nuclear waste repository in basalt. The flows within the study are referred to as the analog flow, in which the alteration effects are the strongest, and the superjacent flow. The analog flow crops out at Grande Ronde River level and a roadcut-outcrop is developed in the flow-top breccia of this flow. The two flows have been divided into flow zones based on intraflow structures observed in the field and primary igneous textures observed in thin section. These zones include, from the base upward, the flow interior, transition, and flow-top breccia zones of the analog flow, the interflow contact zone, and the flow interior and flow-top breccia zone of the superjacent flow. The intraflow structures and textures of the transition and interflow contact zones are atypical of Grande Ronde Basalt flows. The transition zone is transitional in textures between the flow interior zone and flow-top breccia zone, and includes holocrystalline spines mantled with fused in situ breccias. The interflow contact zone reflects the dynamic interaction during the emplacement of the superjacent flow manifested as invasive basalt tongues, clasts shed from tongues, pipe vesicles and tree molds, and pockets of breccia caught up in the base of the superjacent flow.

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3

Davison, Nigel. "The geochemistry of radioactive waste disposal." Thesis, Aston University, 1987. http://publications.aston.ac.uk/9698/.

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The present study attempted to identify the significant parameters which affect radionuclide migration from a low level radioactive waste disposal site located in a clay deposit. From initial sorption studies on smectite minerals, increased Kd with decreasing initial cation concentration was observed, and three sorption mechanisms were identified. The observation of anion dependent sorption was related to the existence of a mechanism in which an anion-cation pair are bound to the clay surface through the anion. The influence of competing cations, typical of inorganic groundwater constituents, depended on: (1) Ni/Co:Mn+(Mn+ = competing cation) ratio, (2) nature of M^n+, (3) total solution ionic strength. The presence of organic material in groundwater is well documented, but its effect on cation sorption has not been established. An initial qualitative investigation involving addition of simple organic ligands to Ni(Co)-hectorite samples demonstrated the formation of metal complexes in the clay interlayers, although some modified behaviour was observed. Further quantitative examination involving likely groundwater organic constituents and more comprehensive physical investigation confirmed this behaviour and enabled separation of the organic compounds used into two classes, according to their effect on cation sorption; (i) acids, (ii) amine compounds. X-ray photoelectron spectroscopy, scanning electron microscopy and Mossbauer spectroscopy were used to investigate the nature of transition metal ions sorbed onto montmorillonite and hectorite. Evidence strongly favoured the sorption of the hexaaquo cation, although a series of sorption sites of slightly different chemical characteristics were responsible for broadened peak widths observed in XPS and Mossbauer investigations. The surface sensitivity of XPS enabled recognition of the two surface sorption sites proposed in earlier sorption studies. Although thermal treatment of Fe^3+/Fe^2+-hectorite samples left iron atoms bonded to the silicate sheet structure, Mossbauer evidence indicated the presence of both ferric and ferrous iron in all samples.

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4

Maiden, Benjamin Gaylord. "Geographic implications of public policy : the siting of noxious facilities /." The Ohio State University, 1986. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487266011225094.

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5

Adkins, Dawn Marie. "A comparison perceived and calculated risk for a low-level radioactive waste disposal facility." Thesis, Georgia Institute of Technology, 1991. http://hdl.handle.net/1853/19683.

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6

McKeown, Christopher. "A model approach to radioactive waste disposal at Sellafield." Thesis, University of Glasgow, 1997. http://theses.gla.ac.uk/2588/.

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Sellafield in West Cumbria is the potential site of a repository for radioactive, Intermediate Level Waste (ILW). The proposed repository lies at 650 m beneath the ground surface to the west of the 1000 m uplands of the Lake District. The fractured Borrowdale Volcanic Group (BVG) host rock is overlain by a sequence of Carboniferous and Permo-Triassic sediments. Fresh, saline and brine groundwaters exist in the subsurface. Upward trending fluid pressure gradients have been measured in the area of the potential repository site. Steady-state, 2-D simulations of fluid flow were undertaken with the OILGEN code. Topographically driven flow dominates the regional hydrogeology. Subsurface fluid flow trended persistently upwards through the potential repository site. The dense brines to the west of the site promoted upward deflection of groundwaters. The groundwater flow rate through the potential repository site was dependent upon the hydraulic conductivity of the BVG. Calibration of the model was achieved by matching simulated subsurface pressures to those measured in-situ. Emergent repository fluids could reach the surface in 15,000 years. The measured BVG hydraulic conductivity is up to 1000 times too high to be simply declared safe. Geochemical simulations, with Geochemist's Workbench?, showed natural BVG groundwaters display redox disequilibrium. The in-situ Eh is most probably +66 mV. Pyrite, absent from rock fractures, would not enforce a reducing -250 mV Eh. Steel barrels and alkaline cement are intended to geochemically retain 2.5x106 kg of uranium. Simulations of repository cement/BVG groundwater interactions produced pH 10 at 80°C but no change in the +66 mV Eh. Steel barrel interactions produced an alkaline fluid with Eh -500 mV. Uranium solubility in the high pH repository near field was as high as 10-2.7 M, regardless of steel interactions. Uranium solubility adjacent to the repository (pseudo near field) was controlled by Eh; ranging from 10-13 M in the presence of steel, to 10-2.7 M with no steel. Uranium retention is controlled only by steel barrel durability. Oxidising, natural BVG groundwater will enhance steel barrel destruction. Distant from repository (far field) uranium solubility was 10-5.4 M if Eh was as measured in-situ. Thermodynamic data variations affect the calculation of uranium solubility; uranium near field solubility can be as high as 10-1.4 M. Uranium solubilities in near-field high pH groundwater could be more than 600 times greater than the 10-5.5 M used by the UK Nirex Ltd. in their safety case simulations.

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7

West, J. M. "Geomicrobiological aspects of the deep disposal of radioactive waste." Thesis, Edinburgh Napier University, 1987. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.379139.

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8

Taiyabi, Asif A. "A multi-attribute analysis of nuclear waste disposal alternatives." Master's thesis, This resource online, 1991. http://scholar.lib.vt.edu/theses/available/etd-02022010-020127/.

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9

Bonnett, Timothy Charles. "A systems view of the nuclear waste dilemma." Master's thesis, This resource online, 1991. http://scholar.lib.vt.edu/theses/available/etd-01202010-020205/.

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10

Creese, Thomas Chalmers. "Use of metamodels in a probabilistic radiological assessment /." Digital version accessible at:, 1998. http://wwwlib.umi.com/cr/utexas/main.

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11

Whang, Jooho. "Migration of radioactive wastes from shallow land burial site under saturated and unsaturated conditions." Diss., Georgia Institute of Technology, 1986. http://hdl.handle.net/1853/16925.

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12

Hoffman, Edward Albert. "Neutron transmutation of nuclear waste." Diss., Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/16700.

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13

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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14

Chemia, Zurab. "Modeling internal deformation of salt structures targeted for radioactive waste disposal." Doctoral thesis, Uppsala University, Department of Earth Sciences, 2008. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-9279.

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This thesis uses results of systematic numerical models to argue that externally inactive salt structures, which are potential targets for radioactive waste disposal, might be internally active due to the presence of dense layers or blocks within a salt layer.

The three papers that support this thesis use the Gorleben salt diapir (NW Germany), which was targeted as a future final repository for high-grade radioactive waste, as a general guideline.

The first two papers present systematic studies of the parameters that control the development of a salt diapir and how it entrains a dense anhydrite layer. Results from these numerical models show that the entrainment of a dense anhydrite layer within a salt diapir depends on four parameters: sedimentation rate, viscosity of salt, perturbation width and the stratigraphic location of the dense layer. The combined effect of these four parameters, which has a direct impact on the rate of salt supply (volume/area of the salt that is supplied to the diapir with time), shape a diapir and the mode of entrainment. Salt diapirs down-built with sedimentary units of high viscosity can potentially grow with an embedded anhydrite layer and deplete their source layer (salt supply ceases). However, when salt supply decreases dramatically or ceases entirely, the entrained anhydrite layer/segments start to sink within the diapir. In inactive diapirs, sinking of the entrained anhydrite layer is inevitable and strongly depends on the rheology of the salt, which is in direct contact with the anhydrite layer. During the post-depositional stage, if the effective viscosity of salt falls below the threshold value of around 10¹⁸-10¹⁹ Pa s, the mobility of anhydrite blocks might influence any repository within the diapir. However, the internal deformation of the salt diapir by the descending blocks decreases with increase in effective viscosity of salt.

The results presented in this thesis suggest that it is highly likely that salt structures where dense and viscous layer/blocks are present undergo an internal deformation processes when these dense blocks start sinking within the diapir. Depending on size and orientation of these blocks, deformation pattern is significantly different within the diapir. Furthermore, model results applied to the Gorleben diapir show that the rate of descent of the entrained anhydrite blocks differs on different sides of the diapir. This suggests that if the anhydrite blocks descent within the Gorleben diapir, they initiate an asymmetric internal flow within it.

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15

Carver, S. J. "Application of geographic information systems to siting radioactive waste disposal facilities." Thesis, University of Newcastle Upon Tyne, 1990. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.315467.

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16

Lockhart, Robert. "Molecular biological characterisation of a low level radioactive waste disposal site." Thesis, University of Liverpool, 2004. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.402321.

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17

VICENTE, ROBERTO. "Gestao de fontes radioativas seladas descartadas." reponame:Repositório Institucional do IPEN, 2002. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11038.

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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

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18

Paukert, Jill G. "Cost effectiveness of schedule compliance in developing a low-level radioactive waste disposal facility in Texas." Thesis, Georgia Institute of Technology, 1988. http://hdl.handle.net/1853/29375.

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19

Ghosh, Sarba Bijoy. "Factors affecting the mobility of selected radionuclides codisposed with municipal refuse within landfills." Thesis, Georgia Institute of Technology, 1987. http://hdl.handle.net/1853/20752.

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20

Powers, Brian Michael. "Characterization of the can-in-canister process /." Full text (PDF) from UMI/Dissertation Abstracts International, 2000. http://wwwlib.umi.com/cr/utexas/fullcit?p3004360.

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21

Thompson, Philip Blinn. "The spatial and temporal distribution of risks associated with low level radioactive waste disposal." Diss., The University of Arizona, 1988. http://hdl.handle.net/10150/184415.

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The disposal of waste is a growing environmental, political, and economic problem. Low level radioactive waste (LLW) disposal is no exception. The major purposes of this dissertation are to examine the economic tradeoffs which arise in the process of LLW disposal and to derive a framework within which the impact of these tradeoffs on LLW disposal policy can be analyzed. There are two distinct stages in the disposal of LLW--the transportation of the waste from sources to disposal sites and the disposal of the waste. The levels of costs and risks associated with these two stages depend on the number and location of disposal sites. Having more disposal sites results in lower transportation costs and risks but also in greater disposal costs and risks. The tradeoff between transportation costs and risks can also be viewed as a tradeoff between present and future risks. Therefore, an alteration in the spatial distribution of LLW disposal sites necessarily implies a change in the temporal distribution of risks. These tradeoffs are examined in this work through the use of a transportation model to which probabilistic radiation exposure constraints are added. Future (disposal) risks are discounted. The number and capacities of LLW disposal sites are varied in order to derive a series of system costs and corresponding expected cancers. This provides policymakers with a cost vs. cancers possibility function. The marginal cost of reducing cancers by changing the number and location of disposal sites is calculated. A possible policy application of this information is illustrated by comparing these costs to an assumed value of life derived from experimental evidence found in the literature. A tentative conclusion is reached that the current movement toward a system of regional LLW disposal sites may be economically suboptimal.

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22

Richter, Jennifer. "New Mexico's nuclear enchantment| Local politics, national imperatives, and radioactive waste disposal." Thesis, The University of New Mexico, 2014. http://pqdtopen.proquest.com/#viewpdf?dispub=3601288.

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The use of nuclear technologies has left an indelible mark on American society. The environmental, political, economic, and social costs of creating, producing, and utilizing technologies such as nuclear weapons and nuclear energy have left a legacy of radioactive waste. To date, there is no comprehensive path for disposing of the different kinds of waste produced by the nuclear industry, including spent nuclear fuel that is now held on site at nuclear power plants. The question of how to deal with nuclear waste has plagued the nuclear industry, governmental agencies, and the concerned public for most of the nuclear era.

There is one permanent geologic repository in the U.S., called the Waste Isolation Pilot Plant (WIPP), located in the salt beds outside of Carlsbad, New Mexico. Presently, WIPP is only allowed to hold low-level transuranic waste produced by military installations during the Cold War. This project looks at the ways that federal attention has turned to this remote site in the Chihuahuan Desert as a potential solution for storing high-level nuclear waste as well. Using ethnographies, archival research, and the ideas expressed at numerous public meeting held in the region, this project shows how nuclear communities are framed in discourses surrounding nuclear waste through the concept of nuclearism, which posits that nuclear technologies are wholly beneficial to society. Specifically, this project examines how concepts involving the immutability of nature and science interact to form problematic assumptions regarding the behavior of the environment in relation to nuclear waste. Furthermore, conversations that focus solely on the production of "sound science" ignore the political and social consequences of creating and moving nuclear waste across the country, ensnaring more communities into the web of potential nuclear consequences. Nuclear issues also intersect different scales, troubling the idea of local consent, the idea of a homogenous public, and whether nuclear technologies can be tools of democracy. The events at the Fukushima nuclear power plant on March 11, 2011 underscored the delicate balance of technology and nature, and showed the inherent vulnerabilities of complex technological systems. By connecting the complex natures of the desert, salt, radiation, and time together with questions of political representation, this project looks at how the nuclear future is being shaped in the desert of New Mexico.

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23

Toprak, Erdem. "Long term response of multi-barrier schemes for underground radioactive waste disposal." Doctoral thesis, Universitat Politècnica de Catalunya, 2018. http://hdl.handle.net/10803/586172.

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The main objective of this thesis is to achieve an improved understanding of the thermo-hydro-mechanical processes and material properties that affect how the gaps and canister) behave during and after installation in the repository. The generated models and methodologies developed in this thesis have provided a deeper understanding of the THM processes taking place in a radioactive spent fuel disposal system and offered strategies for design improvement, material choice and optimization. The Thesis focuses on: - Material characterization (laboratory testing and numerical simulations of these tests), - Thermal dimensioning of repository (fixing canister and tunnel spacing, defining a power decay function for canister, adopting thermal boundary conditions), - 2D THM sensitivity analyses (developing a better understanding of the modelled system, several cases have been studied throughout the thesis), -3 D THM modeling (investigating the effect of variable gas pressure on the thermo-hydro-mechanical results). One of the main contributions of the thesis is to combine comprehensive and complex models to perform the calculations of a single deposition scheme: - BBM (Barcelona Basic Model) to represent clay buffer, BExM (Barcelona Expansive Model) to represent pellet-based components, combined with elasticity to represent rock and canister. - Porosity-dependent permeability and water retention curve (macro-porosity dependent in case of pellets using BExM). - Thermal conductivity depending of degree of saturation. - Gap-specific THM modelling under simplifying assumptions but capturing effects like thermal conductivity that may produce an early peak of temperature, or specific retention curve, which produces extreme, drying near the canister and gap closure that affects swelling pressure development. - Full scale 3D THM modelling with elasto-plastic parameters (BBM) is also an important contribution. The laboratory tests conducted for characterization of materials include: water retention curve tests, thermal conductivity tests, infiltration tests, oedometer tests and tortuosity tests. In general, satisfactory agreement between numerical and measured results is achieved. The majority of 2D sensitivity (fracture position, salinity of the inflow water, rock permeability, filling material between buffer and rock, artificial wetting of pellets etc.) cases show a behavior in safety margins in terms of temperature, density and stresses. A simplified 3D geometry has been adopted for THM calculations to check effect of third dimension. 3D calculations also include a sensitivity analysis. It has been shown that the full saturation of system components is delayed slightly when the air mass balance equation is considered, in other words, a variable gas pressure is taken into account. 3D THM simulations of full scale FISST test (a real scale in situ test will be performed in Onkalo research facility) is considered as a future work to validate, optimize and have better understanding the models and parameters used in the thesis.
El objetivo principal de esta tesis es lograr una mejor comprensión de los procesos termo-hidro-mecánicos y las propiedades del materiales que afectan la forma en que se comportan los componentes del sistema de almacenamiento de los residuos nucleares (barrera arcillosa, relleno, pellets, rocas, huecos y contenedor) durante y después de la instalación en el depósito de residuos. Los modelos y metodologías desarrollados en esta tesis han proporcionado una comprensión más profunda de los procesos de THM que tienen lugar en un sistema de almacenamiento de residuos nucleares y ofrecen estrategias para mejorar el diseño, la selección de materiales y la optimización. La tesis se centra en: - Caracterización de los materiales (ensayos de laboratorio y simulaciones numéricas de estos ensayos), - Dimensionamiento del repositorio (fijación del espaciado entre túneles, definición de una función para la potencia de contenedor con el combustible gastado, adopción de condiciones de contorno térmico), - Análisis de sensibilidad 2D THM (desarrollando una mejor comprensión del sistema modelado, se han estudiado varios casos a lo largo de la tesis). -3D modelo THM (que investiga el efecto de la presión de gas variable en los resultados termo-hidromecánicos). Una de las principales contribuciones de la tesis es combinar modelos completos y complejos para realizar los cálculos de un esquema de repositorio único: - BBM (Barcelona Basic Model) para representar el comportamiento de arcilla no saturada, BExM (Barcelona Expansive Model) para representar componentes como pellets, combinado con modelos de elasticidad para representar roca y el contenedor. - Permeabilidad y curva de retención dependientes de la porosidad (macro-porosidad en el caso de pellets que usan BExM). - Conductividad térmica función del grado de saturación. - Un modelo bi-elastico para representar los huecos. El modelo captura efectos como la conductividad térmica que puede producir un pico temprano de temperatura o curva de retención específica, que produce un secado extremo cerca del contenedor y cierre de huecos, lo que afecta el desarrollo de la presión de hinchamiento. - El modelo de 3D THM a escala real con parámetros elasto-plásticos (BBM) es también una contribución importante. Los ensayos laboratorios realizados para la caracterización de materiales incluyen:ensayo de curva de retención, ensayo de conductividad térmica, infiltración, edómetro y el ensayo de tortuosidad. En general, se logra un acuerdo satisfactorio entre los resultados numéricos y medidos. La mayoría de las analisis de sensibilidad (posición de fractura, salinidad del agua, permeabilidad de la roca, materiales distintos de relleno, condiciones iniciales diferentes para los materiales) muestran un comportamiento en márgenes de seguridad en términos de temperatura, densidad y tensiones. Se ha adoptado una geometría 3D simplificada para los cálculos de THM para verificar el efecto de la tercera dimensión. Los cálculos 3D también incluyen un análisis de sensibilidad. Se ha demostrado que la saturación de los componentes del sistema se retrasa ligeramente cuando se considera la ecuación de balance de masa de aire, en otras palabras, se tiene en cuenta una presión de gas variable. Las simulaciones en 3D de THM del ensayo de FISST a escala real (se realizará un ensayo in situ en la instalación de investigación de Onkalo, Finlandia) se considera un trabajo futuro para validar, optimizar y comprender mejor los modelos y parámetros utilizados en la tesis.

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24

Mackay, R. "Synthetic hydrogeological modelling to explore data worth in radioactive waste disposal assessments." Thesis, University of Newcastle Upon Tyne, 1994. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.261954.

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25

Bassil, Naji Milad. "Cellulose degradation under alkali conditions, representative of cementitious radioactive waste disposal sites." Thesis, University of Manchester, 2015. https://www.research.manchester.ac.uk/portal/en/theses/cellulose-degradation-under-alkali-conditions-representative-of-cementitious-radioactive-waste-disposal-sites(230809e2-41df-43fe-bfc3-a0a1f36a6f67).html.

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Deep geological disposal in a multibarrier cementitious facility is being developed by a number of countries for the safe, long-term disposal of intermediate-level radioactive wastes. Intermediate-level radioactive waste, which dominates the radioactive waste inventory in the United Kingdom on a volumetric basis, is a heterogeneous wasteform that contains organic materials including cellulosic materials, encased in concrete. Under the alkaline conditions expected in the cementitious geological disposal facility (GDF), these materials will undergo abiotic, chemical hydrolysis, and will produce degradation products including isosaccharinic acid (ISA) or gluconic acid (GA) that can form soluble complexes with radionuclides. Alkaliphilic microorganisms sampled from a hyperalkaline site contaminated with lime-kiln waste, were able to degrade cellulosic material (tissue paper) in Ca(OH)2 saturated microcosms at a starting pH of 12. Enzymatic processes in these microcosms caused the production of acetate, acidification of the microcosms and a cessation of ISA production. Enrichment cultures prepared at pH 10 and inoculated with a sediment from the same hyperalkaline site were able to degrade ISA, and couple this degradation process to the reduction of electron acceptors that will dominate as the GDF progresses from an aerobic ‘open phase’ through nitrate- and Fe(III)-reducing conditions post closure. A strictly alkaliphilic bacterium belonging to the Bacillus genus was isolated from the nitrate-reducing enrichment culture, and was found to degrade a variety of organic molecules that are expected to be found in a cementitious GDF. Detailed investigation into the growth of this bacterium suggested that different mechanisms are involved in the biodegradation of ISA and GA, and that bacterial growth is coupled to a decrease in soluble U(VI) concentrations. This implies that microorganisms could have a role in attenuating the mobility of radionuclides in and around a GDF via (i) the biodegradation of cellulose and cessation of ISA production, (ii) the biodegradation of the ligands (ISA and GA) and (iii) the immobilisation of radionuclides. This should facilitate the reduction of undue pessimism in the long-term performance assessment of suchfacilities.

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26

Smith, Kurt. "Radionuclide behaviour in hyperalkaline systems relevant to geological disposal of radioactive waste." Thesis, University of Manchester, 2014. https://www.research.manchester.ac.uk/portal/en/theses/radionuclide-behaviour-in-hyperalkaline-systems-relevant-to-geological-disposal-of-radioactive-waste(0b04ab1b-4392-4cd3-81d7-c2ba02fd782d).html.

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In many countries the current plan for the management of intermediate and high level radioactive wastes is to dispose of the radioactive materials underground in a Geological Disposal Facility (GDF) to prevent release of radioactivity to the environment. In the UK, the repository for intermediate level waste may be backfilled with cementitious material and it is clear that grout and cement will be used during many disposal concepts. Upon saturation, the cement will react creating a region of hyperalkaline geochemical conditions extending away from the GDF, within which, significant changes in radionuclide behaviour are expected. Therefore, this thesis utilises a range of experimental and analytical techniques to try to gain a mechanistic understanding of the behaviour of some key radionuclides (U(VI), Np(V) and Eu(III) as an analogue for Cm(III)/Am(III)) in a range of high pH systems of direct relevance to any cementitious GDF. U(VI) interaction with calcite (calcium carbonate, a common component in high pH cements and the natural environment) surfaces was studied in the 'old' (Ca(OH)2 solution; pH 10.5) and 'young' (Na+, K+, Ca2+; pH 13.3) leachates. In the 'old' leachate, luminescence spectroscopy, batch experiments and kinetic modelling suggested that at low concentrations (smaller or equal to 0.42 µM) a Ca2UO2(CO3)3-like surface complex formed. At higher concentrations, batch experiments, extended X-ray absorption fine structure spectroscopy and luminescence suggested that a surface mediated precipitation mechanism was controlling U(VI) concentrations. Further TEM analysis confirmed that a calcium uranate (CaUO4) solid phase was forming on the calcite surfaces. In the 'young' leachate, batch experiments showed that U(VI) had little affinity for the calcite surface, with no statistically relevant removal from solution observed over a 18 month period. Small angle X-ray diffraction data demonstrated that the U(VI) was probably present in the form of U(VI) intrinsic colloids. Np(V) solubility and sorption to calcite under hyperalkaline conditions were studied using batch, X-ray absorption spectroscopy, and geochemical modelling techniques. It was determined that Np(V) solubility in 'old' cement leachates was consistent with the literature. However, in 'young' cement leachates, an unidentified calcium containing phase was controlling solubility. It was demonstrated that sorption to calcite in 'old' leachates was controlled by the formation of a >CO3NpO2 surface complex, whereas, in the 'young' leachates interaction with the calcite surface was controlled by a precipitation mechanism. Eu(III) sorption to a potential GDF backfill material, Nirex Reference Vault Backfill (NRVB) cement, was studied. The kinetics of removal were rapid with 98.5% Eu(III) removal within 24 hours. Ultrafiltration experiments indicated that all Eu(III) remaining in solution was associated with NRVB derived colloids. Additional experiments using ethylenediaminetetraacetic acid (EDTA) as a competing ligand show that removal from solution was significantly reduced at high concentrations (>0.01 M). These EDTA experiments also indicated some irreversibility in the systems, possibly caused by incorporation into the C-S-H or calcite structures.

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27

Duncan, Ian J. "Radioactive waste : risk, reward, space and time dynamics." Thesis, University of Oxford, 2001. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.365656.

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28

Petelka, Martin Frank. "Leaching of radioactive waste forms under saturated and unsaturated flow conditions." Diss., Georgia Institute of Technology, 1987. http://hdl.handle.net/1853/18224.

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29

Hoag, Christopher Ian. "Canister design for deep borehole disposal of nuclear waste." Thesis, (5 MB), 2006. http://handle.dtic.mil/100.2/ADA473223.

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Thesis (M.S. in Nuclear Science and Engineering)--Massachusetts Institute of Technology, 2006.
"May 2006." Description based on title screen as viewed on June 1, 2010. DTIC Descriptor(s): Boreholes, Radioactive Wastes, Disposal, Canisters, Thermal Properties, USSR, Diameters, Thickness, Stability, Permeability, Environments, Corrosion, Drilling, Flooding, Storage, Reactor Fuels, Nuclear Energy, Barriers, Emplacement, Internal, Fuels, Igneous Rock, Geothermy, Drills, Hazards, Performance (Engineering), Water, Theses, Granite, Steel, Containment (General). Includes bibliographical references (p. 122-125). Also available in print.

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Sun, J. "Carbonation kinetics of cementitious materials used in the geological disposal of radioactive waste." Thesis, University College London (University of London), 2011. http://discovery.ucl.ac.uk/1306875/.

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The use of cement based materials could be widespread in the long term management of radioactive materials in the United Kingdom. In the Geological Disposal Concepts proposed by the Radioactive Waste Management Directorate of the Nuclear Decommissioning Authority (NDA), several cement based materials are used in the long-term management of intermediate-level wastes. Much of the waste will be immobilised within stainless steel containers using cement grouts based on ordinary Portland cement (OPC) blended with blast furnace slag (BFS) or pulverised fuel ash (PFA). The resulting waste packages will be placed underground in a Geological Disposal Facility (or Repository) after a period of storage at the waste producers’ sites. The repository will then be filled with cement based backfill. The encapsulation grouts and the backfill materials will perform as both a physical barrier and chemical barrier for confining the radioactive wastes. During storage and disposal, some wastes may generate carbon dioxide from the degradation of organic materials and this will react with the cement based materials. Therefore, carbonation of the cementitious encapsulation grouts and backfill materials is of interest because of the resulting changes to their physical and chemical properties and also because of its ability to remove carbon-14 labelled carbon dioxide from the gas phase. It is also important to understand the reaction kinetics under a range of conditions, due to the long-term nature of storage and disposal. In this work, the carbonation progress of one backfill material and of two encapsulation grouts used in the UK has been studied in batch reactors. These materials are known as Nirex Reference Vault Backfill (NRVB), 3:1 PFA/OPC and 3:1 BFS/OPC. Based on the single dimensional carbonation experiments, fundamental parameters affecting the rate of carbonation were investigated and the carbon dioxide uptake capacity of each material was determined. For these three materials, an increase in relative humidity (75% to 100%) decreases the carbonation rate. A higher reaction pressure can facilitate the carbonation, but its effect was less obvious than the effect of relative humidity. The progression of the carbonation fronts have also been observed by various techniques and the shape of carbonation front was proved to be influenced by the relative humidity. Special attention was given to the modelling of the kinetics and mechanism of the carbonation reaction of these materials. This work provides fundamental understanding of the carbonation reaction of NRVB, 3:1 PFA/OPC and 3:1 BFS/OPC of relevance to the future optimization of a geological disposal facility in the UK and to assessments of the performance of such a facility.

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Hipkins, Emma Victoria. "Comparing the hydrogeological prospectivity of three UK locations for deep radioactive waste disposal." Thesis, University of Edinburgh, 2018. http://hdl.handle.net/1842/33147.

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The UK has a large and growing inventory of higher activity radioactive waste awaiting safe long term disposal. The international consensus is to dispose of this radioactive and toxic waste within a deep geological repository, situated 200-1,000 metres beneath the ground surface. The deep geological disposal facility is designed to be a series of engineered and natural barriers. Groundwater forms an integral component of the natural barrier because it 1) controls the flux of reactive components towards the engineered repository, and 2) forms one of the primary transport mechanism through which released radionuclides can be transported away from the repository. The timescale of protection provided by the natural barrier exceeds those provided by the engineered barriers. Knowledge of the regional hydrogeology is a vital step towards predicting the long term performance of any potential repository site. Topically, a UK government decision in 2017 to re-open a nation-wide repository location search has now created a renewed mandate for site exploration. This research aims to determine the regional groundwater characteristics of three UK settings, selected to be hydrogeologically distinct, in order to determine which, if any, offers natural long term hydrogeological containment potential. The settings selected for analysis include Sellafield in West Cumbria, the Tynwald Basin within the East Irish Sea Basin, and Thetford within East Anglia. Site selection is based on diverse groundwater characteristics, and on previous research suggesting potential hydrogeological suitability at these locations. This research is novel in that it provides, for the first time, a direct comparison between the characteristics and qualities of different regional groundwater settings to contain and isolate radioactive waste, based on UK site specific data. Large and detailed numerical models for the three sites, covering areas of 30 km length by 2- 4 km depth have been developed using the open source finite element code 'OpenGeoSys'. The models couple the physical processes of liquid flow and heat transport, in order to replicate regional scale groundwater flow patterns. Models are calibrated to measured rock properties, and predict groundwater behaviour 10,000 years into the future. Uncertain parameter ranges of lithological and fault permeabilities, and peak repository temperatures are tested to determine the possible range of groundwater outcomes. Geochemical retention is assessed separately and validated using the finite difference modelling software 'GoldSim'. Worst case groundwater characteristics for containment and isolation at each site are compared to an 'ideal' benchmark far-field hydrogeological outflow scenario, and scored accordingly using a newly proposed method of assessment. Results show that the Tynwald Basin offers the best potential of the three sites for natural radionuclide containment, performing between 3.5 and 4 times better than Sellafield, and between 1.7 and 4 times better than Thetford. The Tynwald Basin is characterised by 1) long and deep groundwater pathways, and 2) slow local and regional groundwater movement. Furthermore, the Tynwald Basin is located at a feasible tunnelling distance from the coast, adjacent to the UK's current nuclear stockpile at Sellafield, and thus could provide a simple solution to the current waste legacy problem. Results from the Sellafield model indicate that this location cannot be considered to exhibit beneficial characteristics due to short and predictable groundwater pathways which ascend, from the repository, towards surface aquifers. Finally, Thetford within East Anglia has never been drilled to depth so that sub-surface rock properties of basement, located beneath layered sediments, are based on evidence inferred from around the UK. Uncertainties in rock properties has produced a wide range of groundwater characteristic possibilities, with results indicting prospective performance to range from 0 to 2.4 times better than Sellafield. As such, the hydrogeological suitability to host a potential deep geological repository is promising when modelled with most-likely permeability values, but cannot be accurately determined at present. Consideration of decaying heat from the heat emitting waste packages at the three sites reveal that the natural groundwater flow patterns can be distorted up to as much as 7 km away from the theoretical repository, depending on setting. This thus changes the use of the term 'near-field' for safety assessments, as implying an area within the immediate vicinity of the excavated repository site. The overarching findings from this research are that: 1) some locations have greater long term radionuclide containment and isolation prospectivity than others, due to variable quality far-field geological and hydrogeological characteristics; 2) the effect of radiogenic heat emission on the natural groundwater flow pattern is dependent on the site specific geological and hydrogeological characteristics, and therefore so is the area defined as the 'near-field'; and 3) a simple method of site comparison is possible for regional groundwater system under steadystate conditions. Recommendations are for scoping models of regional groundwater settings to be used as a comparative tool, such as undertaken as part of this research, to differentiate between potential sites at an early stage of the current UK site selection programme.

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Moyce, Elizabeth Bernice Annwen. "Rock alteration at high pH relevant to the geological disposal of radioactive waste." Thesis, University of Leeds, 2014. http://etheses.whiterose.ac.uk/8914/.

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Dissolution of the cement used in radioactive waste repositories will produce a high pH leachate (pH 10.5-13.1) that will evolve in pH and composition over time, remaining hyperalkaline for 106 years. This will migrate into the repository host rock potentially altering the rock’s physical and chemical properties, and its function as a barrier to radionuclide migration. To investigate the possible alteration over timescales relevant for geological disposal (104 to 105 years), previous studies included short term (< 2 years) laboratory experiments, natural analogue studies (100s to 105 years) and predictive modelling. However, the geochemical and mineralogical processes which may occur as such systems evolve remain poorly constrained. Here, rock alteration in high pH solutions, analogous to cement leachates, has been investigated on short (1 year), medium (15 years) and long (100s years) timescales. The short term investigation agreed with previous studies finding that silicate mineral dissolution and C-S-H precipitation were the predominant alteration processes. In the medium term study, although initially silicate mineral dissolution and C-S-H precipitation occurred, by 15 years of reaction neo-formed Mg-silicates replaced the C-S-H. To investigate rock alteration on a longer timescale Herbert’s Quarry, where high pH fluids have existed for 100s years, was characterised and assessed as a potential analogue site. However, the site was found to have limited applicability in the context of the high pH rock alteration expected at a radioactive waste repository. The impact of rock alteration on U(VI) behaviour was also investigated in the short and medium term. In the short term, U(VI) behaviour during rock alteration varied between solutions representative of different periods of cement leachate evolution, with potential impacts for radionuclide transport. The sorption of U(VI) to unaltered rock and rock altered for 15 years was also investigated. This suggested alteration may increase a rock’s sorption capacity for U(VI).

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Takamura, Hisashi. "A study on wireless transmission monitoring of geological disposal repository for radioactive waste." 京都大学 (Kyoto University), 2007. http://hdl.handle.net/2433/136340.

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Iida, Yoshihisa. "Study on Migration Behavior of Selenium for Safety Assessment of Radioactive Waste Disposal." 京都大学 (Kyoto University), 2012. http://hdl.handle.net/2433/157575.

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35

Berkhout, F. "Radioactive waste : Institutional determinants of management and disposal policy in three European countries." Thesis, University of Sussex, 1989. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.234039.

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The objective of this thesis has been to write a detailed historical account of the policy and practice of radioactive waste management in Britain. Sweden and West Germany, and to draw out implications for theory and public policy. The research was motivated by the perception that many of the technical and socio-political problems of dealing with radioactive wastes had not been resolved. and that these had a critical bearing on the political viability of civil nuclear programmes. By comparing the evolution of the policy process in three countries it has been possible to develop a better understanding of the particular operational. regulatory and political factors determining policy in each case. In addition. fundamental issues in the regulation of radwastes - the setting of standards and criteria for management and disposal, the institutional structure for oversight and policy-making, research policy and its relation to storage. treatment. disposal and siting policy. and the validation of disposal techniques according to performance goals amid great long-term uncertainty - have been clarified through their analysis in a comparative framework. The main conclusions are three-fold. First. the presence or absence of commitments to the reprocessing of spent fuel for a wide range of strategic, industrial and legal reasons have been critical to the success in finding an acceptable radwaste management and disposal policy (or strategy). Politically it is not possible to make a clear distinction between radwaste management and policy for the rest of the back-end of the nuclear fuel cycle. Analytically It is also not possible to separate the two. Second, because of this complex but intimate relationship to reprocessing policy, the dynamism and consistency of radwaste policies are highly dependent on the industrial and political contexts of the drive to reprocessing. Traditionally a view on reprocessing has been virtually synonomous with a faith or scepticism in the future of nuclear power. Experience in the three countries covered in this research shows that there may be a basic conflict between integrated and viable radwaste policies and strong nuclear policies. In this sense radioactive waste could turn out to be the achilles heel of the nuclear industry. Third, the policy process, and indeed its goals, was rather unique to national circumstances (the legal and institutional framework, industrial and political structures). This demonstrates one of the principle arguments of the thesis which is that the innovation process for radwaste management and disposal technologies cannot be seen merely as a technical process, but has to be seen as a process of political and institutional negotiations. There are no perfect' solutions'. Questions of procedure and the context of policy have to be considered as central to the innovation process. Generalizing the patterns which emerge is however difficult, and conclusions must be applied with care under conditions of continuing change and uncertainty.

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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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37

Stone, Michael. "An assessment of the modular high temperature gas-cooled reactor for actinide burning." Thesis, Georgia Institute of Technology, 1991. http://hdl.handle.net/1853/13369.

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38

Stover, Shannon L. "Removal of uranium from aqueous wastes using electrically charged carbon nanofibers." Morgantown, W. Va. : [West Virginia University Libraries], 2000. http://etd.wvu.edu/templates/showETD.cfm?recnum=1769.

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Thesis (M.S.)--West Virginia University, 2000.
Title from document title page. Document formatted into pages; contains ix, 85 p. : ill. (some col.). Includes abstract. Includes bibliographical references (p. 71-74).

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39

Martin, R. Scott. "Chemchar gasification of radioactive, inorganic, and organic laden wastes /." free to MU campus, to others for purchase, 1999. http://wwwlib.umi.com/cr/mo/fullcit?p9946277.

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40

Mohammad, Javeed. "Optimization of high-level waste loading in a borosilicate glass matrix by using chemical durability modeling approach." Master's thesis, Mississippi State : Mississippi State University, 2002. http://library.msstate.edu/etd/show.asp?etd=etd-10282002-160552.

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41

Wang, Qiong. "Hydro-mechanical behaviour of bentonite-based materials used for high-level radioactive waste disposal." Phd thesis, Université Paris-Est, 2012. http://pastel.archives-ouvertes.fr/pastel-00806392.

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This study deals with the hydro-mechanical behaviour of compacted bentonite-based materials used as sealing materials in high-level radioactive waste repositories. The pure MX80 bentontie, mixtures of MX80/crushed claystone and MX80/sand were used in the investigation. An experimental study on the swelling pressure of the bentonite-based materials was first performed. The results evidenced the effects of water chemistry, hydration procedure and duration, pre-existing technological void and experimental methods. Emphasis was put on the relationship between the swelling pressure and the final dry density of bentonite. Afterwards, the water retention test, hydration test and suction controlled oedometer test were conducted on samples with different voids including the technological void and the void inside the soil. By introducing the parameters as bentonite void ratio and water volume ratio, an overall analysis of the effects of voids on the hydro-mechanical response of the compacted material was performed. To get better insight into the seal evolution in case of technological void, the effects of final dry density and hydration time on the microstructure features were also characterized. Then, the hydraulic properties under unsaturated state were investigated by carrying out water retention test and infiltration test as well as the microstructure observation. The results obtained allowed relating the variation of hydraulic conductivity to the microstructure changes. A small scale (1/10) mock up test of the SEALEX in situ experiment was also performed to study the recovery capacity of bentonite-based material with consideration of a technological void. The results were used for interpreting the in-situ observations. With a reduced time scale, it provides useful information for estimating the saturation duration and sealing effectiveness of the field design. Finally, the experimental data obtained in the laboratory on bentonite/sand mixture were interpreted in the framework of the Barcelona Expansive Model (BExM). By comparing the model with the experimental results, the performance and limitation of the model were analyzed

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42

Sultangaliyeva, Fariza. "Formulation of fluid fire-resistant fiber-reinforced cementitious composite : Application to radioactive waste disposal." Thesis, Pau, 2020. http://www.theses.fr/2020PAUU3041.

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Le but de ce travail est de développer un béton fluide résistant au feu renforcé en fibres de polypropylène pour les colis de stockage des déchets radioactifs de moyenne activité à vie longue. Le défi de ce travail consiste à utilizer des fibres de polypropylène qui, même ajoutées en petite quantité, améliorent la résistance au feu mais diminuent de manière significative la maniabilité des bétons frais. Des essais à l’échelle du laboratoire sont effectués afin d’évaluer les comportements rhéologique et à haute température des matériaux cimentaires contenant des fibres de polypropylène. Dans la première partie, une étude du comportement rhéologique des matériaux cimentaires avec des fibres de polypropylène a été réalisée. Le but de cette étude est d’étudier l’influence de ces fibres sur le seuil d’écoulement des pâtes de ciment et des mortiers. Un modèle qui permet d’évaluer la quantité de pâte supplémentaire nécessaire pour compenser l’effet des fibres de polypropylène en fonction de la fluidité du béton frais a été développé.Ensuite, une étude expérimentale et numérique sur le comportement des matériaux cimentaires avec des fibres de polypropylène à haute température a été réalisée afin d’optimiser le choix des fibres pour améliorer la stabilité thermique d’un matériau cimentaire. Des essais de perméabilité résiduelle radiale et des essais feu sur les trois matériaux avec squelettes granulaires différents contenant des fibres de polypropylène de différentes géométries et dosages ont été réalisés dans un but de sélectionner une géométrie et un dosage optimal des fibres. Puis, des simulations thermomécaniques ont été développées à l’échelle macroscopique et mésoscopique. Le choix du diamètre, de la longueur et du dosage des fibres a été fait en fonction de la taille maximale des granulats.Finalement, une méthode de formulation du béton autoplaçant avec des fibres de polypropylène optimisé à la fois du point de vue de la rhéologie et de la résistance au feu a été présentée. Avec cette méthode, la conformité aux critères imposés sur les propriétés à l’état frais et à l’état durci du béton est vérifiée. Des éprouvettes de bétons sont testées sous chargement mécanique uniaxial et, en fonction des résultats, les formulations finales sont sélectionnées pour les futurs essais feu à l’échelle plus importante
The aim of the thesis is to design a self-compacting concrete with polypropylene fibers resistant to fire for a use in storage containers of medium activity long-lived waste. The challenge of the work is presented by the use of polypropylene fibers that enhance fire resistance but drastically diminish workability of concrete even when added at small volume fractions. Tests on laboratory scale are conducted with a purpose of evaluating rheological behavior and high temperature behavior of cementitious materials containing polypropylene fibers.In the first part, a study of rheological behavior of cement-based materials containing polypropylene fibers was done. The aim of this study is to investigate the influence of polypropylene fibers on the yield stress of cement pastes and mortars. A model is proposed to be able to evaluate the quantity of paste necessary to compensate the addition of polypropylene fibres according the fluidity of fresh concrete.Then an experimental and numerical investigation of behavior of cementitious materials with polypropylene fibers at high temperature was done so as to optimize the choice of polypropylene fibers for cementitious material to improve its thermal stability. Three different cementitious materials with three different granular skeleton containing various polypropylene fiber geometries and dosages were tested (residual radial permeability test and fire test) in order to select an optimal fiber geometry and dosage. Then thermomechanical computations was developped at maco and meso scale. Then, a choice of diameter, length and dosage of fibres is proposed according to the maximum size of gravels.Finally, a method of concrete formulation with polypropylene fibers optimized from perspectives of rheology and resistance to fire is presented. In this method, fresh and hardened state properties are verified to ensure an accordance with performance criteria specified by the project. At the end, designed mixes were tested in fire tests conducted on uniaxially compressed prisms and, based on outcomes, final mixes are selected for further fire tests on higher scale concrete

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Gunderson, Katie Marie. "Radiation damage in phosphates and silicates for nuclear waste disposal." Thesis, University of Cambridge, 2013. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.608095.

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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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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

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Green, Ronald T. "Radionuclide transport as vapor through unsaturated fractured rock." Diss., The University of Arizona, 1986. http://etd.library.arizona.edu/etd/GetFileServlet?file=file:///data1/pdf/etd/azu_e9791_1986_348_sip1_w.pdf&type=application/pdf.

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46

Morlando, Rebecca A. "Chemchar gasification of metal-bearing wastes, chlorinated organics and doe surrogate wastes /." free to MU campus, to others for purchase, 1997. http://wwwlib.umi.com/cr/mo/fullcit?p9841325.

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47

Lin, Sheng-Lung. "Effectiveness of sulfur for solidification/stabilization of metal contaminated wastes." Diss., Georgia Institute of Technology, 1995. http://hdl.handle.net/1853/19475.

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TANIMOTO, KATIA S. "Proposta de um questionário destinado a avaliar a percepção de risco relativa a um repositório de rejeitos radioativos." reponame:Repositório Institucional do IPEN, 2011. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10051.

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Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

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Van, Gerven Jesse. "Inconsiderate consideration claims making and the high-level nuclear waste repository at Yucca Mountain, Nevada /." Diss., Columbia, Mo. : University of Missouri-Columbia, 2007. http://hdl.handle.net/10355/5014.

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Thesis (M.A.)--University of Missouri-Columbia, 2007.
The entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file. Title from title screen of research.pdf file (viewed on January 11, 2008) Includes bibliographical references.

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Williams, J. R. (James Robert) 1960. "THE SEALING PERFORMANCE OF BENTONITE/CRUSHED ROCK BOREHOLE PLUGS (NUCLEAR, BASALT, WASTE, REPOSITORY)." Thesis, The University of Arizona, 1986. http://hdl.handle.net/10150/275560.

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Dissertations / Theses on the topic 'Radioactive waste disposal in rivers'

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