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Littérature scientifique sur le sujet « Deep disposal of radioactive waste »

Auteur : Grafiati
Publié le 19 avril 2025

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Articles de revues sur le sujet "Deep disposal of radioactive waste"

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Liu, Jie, Fang Xin Wei et Zhuo Wang. « Environmental Risk of Nuclear Power and Policy Proposal on Disposal of Solid Radioactive Waste ». Advanced Materials Research 726-731 (août 2013) : 2894–97. http://dx.doi.org/10.4028/www.scientific.net/amr.726-731.2894.

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The difficulty occurred in nuclear power plants that the accumulated radioactive solid waste is beyond the design capacity and unable to be sent to disposal is focused on in this paper. The deep reasons for the difficulty occurred are concluded to be the unclear responsibility for disposal of radioactive waste and the divided national function of nuclear power development and radioactive waste management, by analyzing the disposal demand of radioactive solid waste caused by continuous development of nuclear power and the current situation and existing problems for the disposal of low-intermediate level radioactive solid waste in China. The policy suggestions of issuing the disposal siting plan of radioactive solid waste, forming independent firms of radioactive waste storage and disposal and improving radioactive waste management fund system are proposed based on above analysis and investigation.
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Petrenko, Liliana I. « DEEP DISPOSAL THE RADIOACTIVE WASTE IN BOREHOLES ». Collection of Scientific Works of the Institute of Geological Sciences of the NAS of Ukraine 9 (6 juin 2016) : 40–47. http://dx.doi.org/10.30836/igs.2522-9753.2016.144113.

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Mallants, Dirk, Karl Travis, Neil Chapman, Patrick V. Brady et Hefin Griffiths. « The State of the Science and Technology in Deep Borehole Disposal of Nuclear Waste ». Energies 13, no 4 (14 février 2020) : 833. http://dx.doi.org/10.3390/en13040833.

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This Special Issue of the Energies Journal on Deep Borehole Disposal of Nuclear Waste has delivered a timely update on the science and technology of borehole disposal and the types of radioactive wastes it could potentially accommodate. The Special Issue papers discuss (i) circumstances under which a national waste management programme might wish to consider deep borehole disposal; (ii) a status report of deep borehole disposal options in Germany; (iii) the analysis of corrosion performance of engineered barrier systems; (iv) a review of the potential cementing systems suitable for deep borehole disposal; (v) the thermal evolution around heat-generating waste for a wide range of material properties and disposal configurations; (vi) a geochemical analysis of deep brines focussed on fluid-rock interactions; (vii) post-closure performance assessment calculations for deep borehole disposal of Cs/Sr capsules and an example safety case for (viii) horizontal and (ix) vertical deep borehole disposal of nuclear wastes.
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Понизов, А. В. « A SYSTEM OF ORGANIZATIONAL AND TECHNICAL MEASURES FOR SAFE CLOSURE OF DEEP DISPOSAL FACILITIES FOR LIQUID RADIOACTIVE WASTE.CONCEPTUAL PROVISIONS ». ЯДЕРНАЯ И РАДИАЦИОННАЯ БЕЗОПАСНОСТЬ, no 4(98) (22 décembre 2020) : 47–60. http://dx.doi.org/10.26277/secnrs.2020.98.4.005.

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Проведен анализ опыта ликвидации эксплуатационных скважин на пунктах глубинного захоронения жидкихрадиоактивных отходов. Определены количественные показатели, относящиеся к ликвидации скважин на примере пункта глубинного захоронения жидких радиоактивных отходов «Димитровградский».С учетом требований федеральных норм и правил в области использования атомной энергии по обеспечению безопасности закрытия пункта глубинного захоронения жидких радиоактивных отходов сформулированы и систематизированы концептуальные положения о системе организационно-технических мер, необходимых для безопасного закрытия пункта глубинного захоронения жидких радиоактивных отходов, применительно к варианту «немедленное закрытие». The analysis of the experience of the closure of operational boreholes of deep disposal facilities for liquid radioactive waste was performed. Quantitative criteria related to the closure of the deep disposal facilities for liquid radioactive waste “Dimitrovgrasky” boreholes were specified.Conceptual proposals to the organizational and technical measures required for the safe closure of the deep disposal facilities for liquid radioactive waste as applied to «immediate» closure option have been specified and systematized based on the federal rules and regulations in the field of atomic energy use that establish safety requirements for the closure of the deep disposal facilities for liquid radioactive waste.
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Tyler, Paul A. « Disposal in the deep sea : analogue of nature or faux ami ? » Environmental Conservation 30, no 1 (mars 2003) : 26–39. http://dx.doi.org/10.1017/s037689290300002x.

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The deep sea is the world's largest ecosystem by volume and is assumed to have a high assimilative capacity. Natural events, such as the sinking of surface plant and animal material to the seabed, sediment slides, benthic storms and hydrothermal vents can contribute vast amounts of material, both organic and inorganic, to the deep ocean. In the past the deep sea has been used as a repository for sewage, dredge spoil and radioactive waste. In addition, there has been interest in the disposal of large man-made objects and, more recently, the disposal of industrially-produced carbon dioxide. Some of the materials disposed of in the deep sea may have natural analogues. This review examines natural processes in the deep sea including the vertical flux of organic material, turbidity currents and benthic storms, natural gas emissions, hydrothermal vents, natural radionuclides and rocky substrata, and compares them with anthropogenic input including sewage disposal, dredge spoil, carbon dioxide disposal, chemical contamination and the disposal of radioactive waste, wrecks and rigs. The comparison shows what are true analogues and what are false friends. Knowledge of the deep sea is fragmentary and much more needs to be known about this large, biologically-diverse system before any further consideration is given to its use in the disposal of waste.
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Kim, Jihye, Seongmuk Lee, Heejeong Choi, Hyunyoung Park et Sokhee P. Jung. « Global Radioactive Waste Disposal Trends and Prospects ». Journal of Korean Society of Environmental Engineers 45, no 4 (30 avril 2023) : 210–24. http://dx.doi.org/10.4491/ksee.2023.45.4.210.

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Nuclear power generation, which began in the Soviet Union in June 1954, has now become a main source of electrical energy in 33 countries around the world. However, radioactive waste and its safety have always been at the center of controversy, and even after 70 years, there is no official regulation on the disposal of radioactive waste under international law. In this review, the policies and current status of radioactive waste disposal in major countries around the world, including Korea, are investigated. Based on this, the direction for radioactive waste management in Korea was presented. Currently, radioactive waste is disposed of in two ways. Finland, Sweden, and France are conducting deep permanent disposal according to the recommendation of the International Atomic Energy Agency, and Japan, the United Kingdom, and India are promoting reprocessing of spent nuclear fuel to reduce waste and the volume of the repository. Korea has been temporarily storing radioactive waste at the site of the power plant since the completion of Kori Unit 1 in 1978, but it is expected that the capacity of the temporary storage facility will reach its limit in 2031. Accordingly, the securing of a permanent disposal site and the development of reprocessing technology are being studied together, but no tangible results have been achieved so far. Korea's radioactive waste disposal has problems such as a small land area, institutional difficulties in developing reprocessing technology, frequent policy changes, ignorance and indifference, and lack of smooth communication. Although public concern about nuclear power generation has increased due to the Fukushima disaster, not many people are interested in spent nuclear fuel. Within the framework of reprocessing and permanent disposal, Korea should refrain from frequent policy changes that can confuse public opinion and research and development, and come up with a long-term realistic policy.
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Palmu, M., T. Eng et T. M. Beattie. « Towards an 'implementing geological disposal technology platform' in Europe ». Mineralogical Magazine 76, no 8 (décembre 2012) : 3439–44. http://dx.doi.org/10.1180/minmag.2012.076.8.57.

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AbstractSeveral European waste management organizations have started work on creating a technology platform to accelerate the implementation of deep geological disposal of radioactive waste in Europe. There is an increasing consensus in the international community about geological disposal as the preferred option for solving the long-term management of spent fuel, high-level waste and other longlived radioactive wastes. At the same time, European citizens have a widespread desire for a permanent solution for high-level radioactive waste disposal. A majority of European countries with nuclear power have active waste-management programmes, but the current status and the main challenges of those programmes vary. The most advanced waste management programmes in Europe (i.e. those in Sweden, Finland and France) are prepared to start the licensing process of deep geological disposal facilities within the next decade. Despite the differences between the timing and the challenges of the different programmes, there is a joint awareness that cooperation on the scientific, technical and social challenges related to geological disposal is needed, and that it is beneficial for the timely and safe implementation of the first geological disposal facilities. Such a demonstration of a viable solution for the management of high-level radioactive waste will enhance stakeholder confidence in Europe. It is envisaged that a technology platform would enhance European cooperation in this area. The platform will provide a tool for reducing overlapping work, to produce savings in total costs of research and implementation, and to make better use of existing competence and research infrastructures. From 2008, SKB (Sweden) and Posiva (Finland) led the preparation work to set up the implementing geological disposal of radioactive waste technology platform (IGD-TP). Since then other implementers from France, Germany, Switzerland, United Kingdom, Spain and Belgium have joined the project. To date a strategic research agenda for the platform has been prepared and consulted upon, which is now the basis for taking the platform into a deployment phase.
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Muller, Richard A., Stefan Finsterle, John Grimsich, Rod Baltzer, Elizabeth A. Muller, James W. Rector, Joe Payer et John Apps. « Disposal of High-Level Nuclear Waste in Deep Horizontal Drillholes ». Energies 12, no 11 (29 mai 2019) : 2052. http://dx.doi.org/10.3390/en12112052.

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Spent nuclear fuel and high-level radioactive waste can be disposed in deep horizontal drillholes in sedimentary, metamorphic or igneous rocks. Horizontal drillhole disposal has safety, operational and economic benefits: the repository is deep in the brine-saturated zone far below aquifers in a reducing environment of formations that can be shown to have been isolated from the surface for exceedingly long times; its depth provides safety against inadvertent intrusion, earthquakes and near-surface perturbations; it can be placed close to the reactors and interim storage facilities, minimizing transportation; disposal costs per ton of waste can be kept substantially lower than for mined repositories by its smaller size, reduced infrastructure needs and staged implementation; and, if desired, the waste could be retrieved using “fishing” technology. In the proposed disposal concept, corrosion-resistant canisters containing unmodified fuel assemblies from commercial reactors would be placed end-to-end in up to 50 cm diameter horizontal drillholes, a configuration that reduces mechanical stresses and keeps the temperatures below the boiling point of the brine. Other high-level wastes, such as capsules containing 137Cs and 90Sr, can be disposed in small-diameter horizontal drillholes. We provide an overview of this novel disposal concept and its technology, discuss some of its safety aspects and compare it to mined repositories and the deep vertical borehole disposal concept.
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Wanner, Hans. « Solubility data in radioactive waste disposal ». Pure and Applied Chemistry 79, no 5 (1 janvier 2007) : 875–82. http://dx.doi.org/10.1351/pac200779050875.

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Radioactive waste arises mainly from the generation of nuclear power but also from the use of radioactive materials in medicine, industry, and research. It occurs in a variety of forms and may range from slightly to highly radioactive. It is a worldwide consensus that radioactive waste should be disposed of in a permanent way which ensures protection of humans and the environment. This objective may be achieved by isolating radioactive waste in a disposal system which is located, designed, constructed, operated, and closed such that any potential hazard to human health is kept acceptably low, now and in the future.For highly radioactive waste and spent nuclear fuel, which are the waste types representing the highest potential danger to human health, an effective isolation from the biosphere is considered to be achievable by deep geological disposal. Disposal concepts rely on the passive safety functions of a series of engineered and natural barriers. Since total isolation over extended timescales is not possible, radionuclides will eventually be released from the waste matrix and migrate through the engineered and natural barriers. The assessment of their mobility in these environments is essential for the safety demonstration of such a repository. The solubility of many radionuclides is limited and may contribute significantly to retention. Reliable predictions of solubility limitations are therefore important.Predictions of maximum solubilities are always subject to uncertainties. Complete sets of thermodynamic and equilibrium data are required for a reliable assessment of the chemical behavior of the radionuclides. Gaps in the thermodynamic databases may lead to erroneous predictions. Missing data and insufficient knowledge of the solubility-limiting processes increase the uncertainties and require pessimistic assumptions in the safety analysis; however, these are usually not detrimental to safety owing to the robustness of the multi-barrier approach.
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Englert, Matthias, Simone Mohr, Saleem Chaudry et Stephan Kurth. « Alternative Disposal Options for High-Level Radioactive Waste ». Safety of Nuclear Waste Disposal 1 (10 novembre 2021) : 259–60. http://dx.doi.org/10.5194/sand-1-259-2021.

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Abstract. Are alternatives to the disposal of high-level radioactive waste in a geology repository conceivable? We present the results of the first phase of a research project on the state of the art in science and technology for alternative disposal options. The project is financed by the Federal Office for the Safety of Nuclear Waste Management. Most recently, in 2015, the German Commission on the Storage of High-Level Radioactive Waste (Endlagerkommission) evaluated possible disposal technologies and classified them as either promising, conceivable, or to be pursued further. Only final disposal in a geological repository was considered promising. Conceivable, but not immediately available or not advantageous, were storage in deep boreholes (DBs), long-term interim storage (LTIS), and partitioning and transmutation (P&T). All other alternative disposal options by burial, dilution, or removal from the planet were determined not to be worth pursuing. The Disposal Commission did conclude that none of the three conceivable methods (DBs, LTIS, P&T) would result in earlier disposal of high-level radioactive waste than the preferred final disposal in a mine. However, it recommended continued tracking and regular monitoring of the future development of alternative disposal options, e.g., disposal in deep boreholes. Finally, in 2017, with the amended Site Selection Act, the federal government specified disposal in a repository mine with the option of retrieval during operation or recovery for 500 years after closure. In a learning site selection process, the Federal Office for the Safety of Nuclear Waste Disposal (BASE) reviews the proposals of the project managing company, the Federal Company for Radioactive Waste Disposal (BGE), and prepares a reasoned recommendation to the federal government for a site with the best possible safety. Part of the reasoned recommendation is, among other things, a discussion of alternative disposal options to final disposal in deep geological formations. In the presentation, we report on the status of international research on alternative disposal options, discuss advantages and disadvantages of the technologies, and evaluate the potential of the technologies for the disposal of high-level radioactive waste in Germany. The LTIS is designed as dry storage in a building to be constructed above ground or near the surface and is expected to last for a period of several hundred years. With LTIS it would be possible to gain time for the development of a suitable final disposal option; however, this also postpones the disposal issue indefinitely into the future with undetermined methods. DB storage would involve sinking the storage containers into boreholes with depths of up to 5000 m. This could reduce the expense and be particularly advantageous for smaller inventories, although the potential for the use of engineered barriers would be limited and retrievability precluded according to the current state of the art in science and technology. P&T is primarily intended to separate long-lived transuranic elements from high-level radioactive waste and then convert them to short-lived fission products by neutron irradiation in reactors. The main goal is to reduce the necessary containment times in the repository by changing the inventory, but the effort to treat the waste would be significant and a repository for high-level nuclear waste is still needed. More exotic ideas for alternative disposal include deep geological injection of liquid waste, waste forms that melt themselves into rock, storage inside the ocean floor or subduction zones, shipment to space, burial in ice sheets, or dilution in the atmosphere and oceans. None of these exotic options is currently being actively pursued.
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Thèses sur le sujet "Deep disposal of radioactive waste"

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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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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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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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Yang, Ting. « Maturation of Clay Seals in Deep Bore Holes for Disposal of Radioactive waste : Theory and Experiments ». Doctoral thesis, Luleå tekniska universitet, Geoteknologi, 2017. http://urn.kb.se/resolve?urn=urn:nbn:se:ltu:diva-65794.

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KBS-3 and very deep borehole (VDH) concepts are two major types of long-term geologicaldisposal methods for high-level radioactive waste (HLW) isolating from the biosphere. TheKBS-3V concept for isolating the HLW at the depth of 400-500 m, is the officially proposedoption in Sweden and has been the subject of considerable research in the past few decades,while the VDH concept was considered as an option in the 1950s but later became discouragedbecause of insufficient experience in drilling technology. The greatest merit of the VDHconcept is that the almost stagnant groundwater in the deep boreholes prevents the transport ofthe possible release of radionuclides into the rock or up to the ground level. Since variousdisadvantages of the KBS-3V concept were found in previous research, the superiority of VDHconcept attracted the researchers to continue studying it into the late 1980s.The geological repositories of both of KBS-3V and VDH types primarily consist of a naturalbarrier (host rock) and of an engineering barrier (also known as a buffer/backfill barrier).According to the principle of IAEA and national relative research organizations, thebuffer/backfill material should have low permeability and good expandability, as well assuitable physical and sealing properties.The thesis concerns the VDH concept and is focused on the construction and performance ofthose parts of the sealed repository that are not affected by high temperature or gamma radiation.In the lower part of a VDH repository, the clay packages containing HLW will be exposed tohigh temperature (100-150 􀄇 ) in the borehole and to highly saline groundwater. In theinstallation phase of HLW, the groundwater will be pumped out and replaced by medium-softsmectite clay mud in which the HLW packages are installed vertically. During the hydrationand maturation of the clay components, the microstructural reorganization, water transport,migration of clay particles and redistribution of the density of the components take place. Thematuration determines the transient evolution of the clay seals and influences the rheologicaland soil mechanical behavior in the installation phase. The maturation of clay system alsodetermines their ultimate sealing potential of VDH repositories.This study presents the work carried out for investigating the maturation of the buffer-backfillclay in the HLW deep borehole. Initially in the study three types of clays, the Namontmorillonite,magnesium-rich and illite-smectite mixed layer clays, were examined for estimating their performance as the barrier candidate material. This is mainly presented in theliterature review. The experimental study was conducted on montmorillonite GMZ clays andI/S mixed-layer Holmehus clay. The expandability and permeability tests were carried out forinterpretation of the recorded swelling development and assessment of the effect of the salineconditions, with the goal of deriving a relationship between swelling pressure and hydraulicconductivity for different dry densities. The maturation tests of initially fully-saturatedHolmehus clay and partly saturated GMZ clay were performed. During the tests, the shearstrength mobilised by the relative movement of densified mud and migrated dense clay -contained in a perforated central tube - were determined. According to the results of shearstrength tests, the maximum operation time or the number of clay packages to be placed in asingle operation was evaluated, whilst the suitable saturation degree of the dense clay wasdiscussed as well.A model of the maturation of initially water-saturated clay seals based on Darcy’s law wasworked out and the evolution of the clay components in a lab-scale borehole using Holmehusclay were performed and compared with the experimental recordings. Good agreementsbetween the physical behaviors of the theoretical simulations and the measurements wasachieved by which the validity of the model was verified. Using the results, the hydration andsoil migration in the entire maturation process were presented in diagram. The model was alsoused for preliminary evaluation of the maturation products in real boreholes by assuming thesame Holmehus clay as used in the tests. Two constellation of borehole and dense clay withdifferent diameters, 80 cm borehole /60 cm clay and 80cm/50cm, were assumed. The resultsrespecting dry density and hydraulic conductivity of the ultimate maturation products, and thedegree of homogeneous of the buffer and backfill clay system in the assumed boreholes, arepresented and discussed. The options of different mineral types and initial physical propertiesof the candidate buffer clays provide a reference for engineering barrier design of HLW disposalin VDH.
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Bahlouli, Mohamed Haythem. « Modélisation couplée des écoulements liquide-gaz et de l'hydro-mécanique dans un stockage géologique de déchets radioactifs ». Electronic Thesis or Diss., Université de Toulouse (2023-....), 2025. http://www.theses.fr/2025TLSEP028.

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Le stockage géologique profond constitue la solution internationale la plus prometteuse pour la gestion des déchets les plus radioactifs et à durée de vie longue sur de très longues échelles de temps. En France, le projet Cigéo vise à stocker les déchets dits de haute activité (HA), principalement issus des combustibles usés des centrales nucléaires après retraitement et les déchets de moyenne activité à vie longue (MA-VL), qui correspondent aux structures métalliques qui entourent le combustible ou aux résidus liés au fonctionnement et à la maintenance des installations nucléaires. La sûreté du stockage est assurée par un système multi-barrières composé de barrières ouvragées et une roche hôte. Grâce à sa très faible conductivité hydraulique, sa faible diffusion moléculaire et sa capacité significative de rétention des radionucléides, l’argilite du Callovo-Oxfordien (COx) est considérée comme la formation géologique potentielle pour la réalisation du projet. Or, après la fermeture et le scellement de l'installation souterraine, une quantité significative de gaz (principalement de l’hydrogène) peut être générée en raison de plusieurs processus tels que la corrosion anaérobie des métaux, la radiolyse de l'eau et les réactions microbiennes. Si le transitoire hydraulique-gaz des installations souterraines a été très étudié au cours des deux dernières décennies, la représentation de certains processus fortement couplés tels que les écoulements diphasiques multi-composants dans des matériaux poreux très faiblement perméables, à des différentes échelles spatiales et l'hydro-mécanique restent potentiellement complexe. La présente étude a été réalisée à l’Unité d’expertise et de modélisation des installations de stockage, à l'Institut de radioprotection et de sûreté nucléaire. L'objectif était d'améliorer la robustesse des modélisations du comportement hydrodynamique des phases liquide-gaz et traiter la problématique des impacts mécaniques des déformations de la roche et des scellements sur le transport de gaz et vice versa. Seules des simulations numériques sont capables de rendre compte de l’ensemble des phénomènes sur les échelles d’espace et de temps à considérer. Pour cela, deux approches ont été suivies. Une étude analytique de l'écoulement monophasique gaz a été effectuée afin d'évaluer la sensibilité des phénomènes d'écoulement du gaz aux divers paramètres physiques, y compris la compressibilité et l'effet Klinkenberg. Parallèlement, des simulations numériques ont été réalisées sur un modèle d'alvéole de déchets HA. Elles ont permis de mettre en évidence l'évolution de la pression du gaz et la désaturation de la roche hôte et des scellements. Ces simulations prennent en compte la présence de l'air dans la phase gaz, afin d’appréhender le poids d'une atmosphère explosive en lien avec l'inflammabilité de l'hydrogène dans l'air. Ces études étaient aussi le terrain pour introduire des améliorations dans le code TOUGH2 et de développer des outils de pre- et de post- processing qui facilitent l'utilisation de ce code et l'analyse des résultats. Concernant le couplage hydromécanique, une revue bibliographique approfondie est réalisée, et a permis d'isoler les problèmes soulevés par le couplage poro-élastique en présence de gaz. Un modèle d'élasticité linéaire avec un couplage HM basé sur la théorie de Biot est ensuite étudié et implémenté dans le logiciel COMSOL Multiphysics en utilisant la méthode des éléments finis. Des simulations numériques de tests hydro-mécaniques drainés ou non-drainés ont été réalisés. Le couplage a permis de capturer l'interaction entre la variation de pression du fluide et les contraintes et déformations dans la roche poreuse. Un des résultats est la mise en évidence de la production fluide
As a safe long-term management of nuclear waste, deep geological disposal was proposed and is the widely accepted approach to deal with high-level radioactive waste. It is currently being under study in several countries. The long-term safety in a deep geological repository (DGR) is ensured through a multi-barrier system provided by engineered barrier and natural barrier systems. In most multi-barrier system concepts in crystalline and clay rock, argillaceous materials (clay rock or bentonite) are envisaged to use for barrier elements. Due to its very low hydraulic conductivity, low molecular diffusion and significant radionuclide retention capacity, COx claystone is considered as a potential geological host formation for an industrial radioactive waste repository in France. The performance of the host rock and engineered barriers in the construction phase and in a long-term perspective (thousands to million of years) is of primary importance for predicting the risk of dissemination of radioactivity. After the deep geological repository is closed and sealed, significant gas quantity can be generated due to several processes such as the anaerobic metal corrosion, water radiolysis and microbial reactions. Predicting gas flow in low-permeable, saturated materials is a challenging but important task in the risk assessment of a deep geological repository. Pressure build-up and gas migration in host rock and engineered barriers constitute a highly coupled hydro-mechanical (HM) process, and may contribute to the development of preferential gas pathways either by gas-induced micro-fracturing or macro-fracturing. In current numerical studies some behaviors still cannot be well represented, in particular, it is challenging to explain the gas migration behavior in the gas injection tests conducted on the clayey rock and barriers materials. Therefore, to better represent the actual physical process of gas flow, several modeling frameworks are proposed in the present thesis: single-phase gas flow (H2), two-phase water-gas multi-component flow (air, H2), and hydro-mechanical coupling (poro-elasticity). Two-phase gas-water flow in the waste cell model at different scales (a single waste cell contains several High Level Waste containers) is used here to quantitatively study transient hydraulic water-gas phenomena, such as gas pressure evolution and clayey rock desaturation. A wide range of scenarios and hypotheses is tested to assess significant differences between different scenarios in controlling gas migration and the transition from single phase water saturated conditions to two-phase and single phase gas. Although efficient in studying gas migration in presence of hydrogen only, the proposed models has presented a major limitation because of the difficulty in assessing gas phase evolution in presence of air. Multiphase flow of water with a gas phase (hydrogen and air) together with consideration of dissolved hydrogen, air and water vapor diffusion, is studied using equation of state EOS7R (water, brine, RN1, RN2, air) of the TOUGH2 family of codes. We have implemented code enhancements and post-processing scripts, which enhanced our capabilities in analyzing and interpreting results. A separate study of single phase gas flow was developed in order to assess analytically the sensitivity of gas flow phenomena to various rock parameters, including for instance the Klinkenberg effect due to gas slippage at low pressure in tight pores. Concerning the hydromechanical coupling, an extensive review was developed, including poroelastic coupling in the presence of gas. A linear poroelastic model based on Biot theory is studied and implemented in the Finite Elements software COMSOL Multiphysics. The coupling allows us to capture the interaction between fluid pressure variation and the stresses and strains in the porous rock (drained and undrained tests)
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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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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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Esnault, Loïc. « Réactivité géomicrobiologique des matériaux et minéraux ferrifères : impact sur la sureté d'un stockage de déchets radioactifs en milieux argileux ». Thesis, Nancy 1, 2010. http://www.theses.fr/2010NAN10139/document.

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Cette thèse s'est attachée à décrire le concept dynamique d'une activité microbiologique viable et durable en conditions de stockage géologique profond et à évaluer son impact sur les propriétés de confinement et les composants du stockage. Ainsi, dans cette étude, un modèle bactérien basé sur la ferriréduction a été choisi pour ses critères de viabilité dans le système et sa capacité à altérer les matériaux dans les conditions du stockage. Les principaux résultats de ce travail de thèse ont permis de démontrer la capacité du milieu à supporter l'activité bactérienne ferriréductrice et les conditions de son développement dans les environnements argileux profonds. Il a été clairement montré la biodisponibilité du Fe(III) structural des matériaux argileux et des oxydes de fer produits lors des processus de corrosion métallique. Dans ce système, la corrosion paraît être un facteur positif pour les activités bactériennes notamment en produisant une source énergétique, l'hydrogène. Les activités bactériennes ferriréductrices peuvent entraîner une reprise de la corrosion métallique via la consommation des oxydes de fer de la couche passivante. La conséquence directe pourrait être une diminution de la durée de vie des enveloppes métalliques de colisage. Dans le cas des matériaux argileux ferrifères, les conséquences d'une telle activité sont telles qu'elles peuvent avoir un impact sur l'ensemble de l'édifice poreux que ce soit en termes de réactivité chimique des matériaux ou de comportement physique de la barrière argileuse. Un des résultats les plus marquants est la cristallisation de nouvelles phases argileuses à des températures très basses, inférieures à 40°C, témoignant de l'influence considérable de l'activité microbienne anaérobie dans les transformations minéralogiques des minéraux argileux. De plus, il faut noter que ces expériences ont permis de visualiser pour la première fois un mécanisme de respiration bactérienne à distance via une extension de la disponibilité d'éléments essentiels, ici le Fe3+. En conclusion, ces résultats ont clairement démontré l'impact du facteur microbiologique sur la réactivité des matériaux argileux et métalliques tout en s'appuyant sur des paramètres de contrôle de l'activité bactérienne. La pertinence de la prise en compte de ces activités microbiologiques dans le cas des évaluations de sûreté d'un stockage est ainsi établie
This thesis sought to describe the dynamic concept of a viable and sustainable microbiological activity under deep geological disposal conditions and to assess its impact on containment properties and storage components. Thus, in this study, a model based on the bacterial ferric reduction was chosen for its sustainability criteria in the system and its ability to alter the materials in storage conditions. The main results of this work demonstrated the capability of the environment to stand the iron-reducing bacterial activity and the conditions of its development in the deep clay environments. The bio-availability of structural Fe (III) in clay minerals and iron oxides produced during the process of metal corrosion was clearly demonstrated. In this system, the corrosion appears to be a positive factor on bacterial activities by producing an energy source, hydrogen. The iron-reducing bacterial activities can lead to a resumption of metallic corrosion through the consumption of iron oxides in the passive film. The direct consequence would be a reduction of the lifetime of metal containers. In the case of ferric clay minerals, the consequences of such an activity are such that they can have an impact on the overall porous structure both in terms of chemical reactivity of the materials or physical behavior of the clayey barrier. One of the most significant results is the crystallization of new clay phases at very low temperatures, below 40°C, highlighting the influence of the anaerobic microbial activity in the mineralogical transformations of clay minerals. Furthermore, these experiments also allowed to visualize, for the first time, a mechanism of bacterial respiration at distance, this increases the field of the availability of essential elements as Fe3+ for bacterial growth in extreme environment. In conclusion, these results clearly showed the impact of the microbiological factor on the reactivity of clay and metal minerals, while relying on control parameters on bacterial activity. The relevance of taking into account these microbiological activities in the case of safety assessments of a repository is then established
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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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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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Livres sur le sujet "Deep disposal of radioactive waste"

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R, Alexander W., et McKinley L. E, dir. Deep geological disposal of radioactive waste. Amsterdam : Elsevier, 2007.

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Compton, Keith L. Deep well injection of liquid radioactive waste at Krasnoyarsk-26. Laxenburg, Austria : International Institute for Applied Systems Analysis, 2000.

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IMO/FAO/UNESCO/WMO/WHO/IAEA/UN/UNEP Joint Group of Experts on the Scientific Aspects of Marine Pollution et International Atomic Energy Agency, dir. An Oceanographic model for the dispersion of wastes disposed of in the deep sea. Vienna : International Atomic Energy Agency, 1986.

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International, Conference on Deep Geological Disposal of Radioactive Waste (1996 Winnipeg Man ). Proceedings of the 1996 International Conference on Deep Geological Disposal of Radioactive Waste : September 16-19, 1996, Winnipeg, Manitoba Canada. Toronto : Canadian Nuclear Society, 1996.

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Walden, Barrie B. Recovery of low-level radioactive waste packages from deep ocean disposal sites. Woods Hole, Mass : Woods Hole Oceanographic Institution, 1987.

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Walden, Barrie B. Recovery of low-level radioactive waste packages from deep ocean disposal sites. Woods Hole, Mass : Woods Hole Oceanographic Institution, 1987.

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Wuschke, D. M. Assessment of the long-term risks of inadvertent human intrusion into a disposal vault in deep plutonic rock : Reassessment using ICRP recommendations. Pinawa, Man : Whiteshell Laboratories, 1996.

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Wuschke, D. M. Assessment of the long-term risks of inadvertent human intrusion into a proposed Canadian nuclear fuel waste disposal vault in deep plutonic rock. Pinawa, Man : Whiteshell Laboratories, 1996.

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1957-, Metcalfe Douglas Earle, OECD Nuclear Energy Agency et Working Group on Integrated Performance Assessments of Deep Repositories., dir. Establishing and communicating confidence in the safety of deep geologic disposal : approaches and arguments = : Établir et faire partager la confiance dans la sûreté des dépôts en grande profondeur : approches et arguments. [Paris] : Nuclear Energy Agency. Organisation for Economic Co-operation and Development, 2000.

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Agency, International Atomic Energy, dir. Deep underground disposal of radioactive wastes : Near-field effects. Vienna : International Atomic Energy Agency, 1985.

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Chapitres de livres sur le sujet "Deep disposal of radioactive waste"

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Glasbergen, P. « Hydrological Model Studies and Natural Isotope Data as Indication for Groundwater Flow in Deep Sedimentary Basins ». Dans Natural Analogues in Radioactive Waste Disposal, 420–35. Dordrecht : Springer Netherlands, 1987. http://dx.doi.org/10.1007/978-94-009-3465-8_36.

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Shao, Haibing, Ju Wang, Thorsten Schäfer, Chun-Liang Zhang, Horst Geckeis, Thomas Nagel, Uwe Düsterloh, Olaf Kolditz et Hua Shao. « Introduction ». Dans Thermo-Hydro-Mechanical-Chemical (THMC) Processes in Bentonite Barrier Systems, 1–4. Cham : Springer Nature Switzerland, 2024. http://dx.doi.org/10.1007/978-3-031-53204-7_1.

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Hoek, Jaap. « Deep-Well Injection of Radioactive Waste in Russia ». Dans Defence Nuclear Waste Disposal in Russia : International Perspective, 219–30. Dordrecht : Springer Netherlands, 1998. http://dx.doi.org/10.1007/978-94-011-5112-2_19.

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McEwen, T. J. « Geological Aspects of the Deep Disposal of Radioactive Waste ». Dans Defence Nuclear Waste Disposal in Russia : International Perspective, 99–120. Dordrecht : Springer Netherlands, 1998. http://dx.doi.org/10.1007/978-94-011-5112-2_8.

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Rybalchenko, A. « Deep-Well Injection of Liquid Radioactive Waste in Russia : Present Situation ». Dans Defence Nuclear Waste Disposal in Russia : International Perspective, 199–217. Dordrecht : Springer Netherlands, 1998. http://dx.doi.org/10.1007/978-94-011-5112-2_18.

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Semenov, G. G. « Comments on Seismic Considerations with Respect to Deep Radioactive Waste Disposal ». Dans Defence Nuclear Waste Disposal in Russia : International Perspective, 317–19. Dordrecht : Springer Netherlands, 1998. http://dx.doi.org/10.1007/978-94-011-5112-2_26.

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Buschaert, Stéphane, et Sylvie Lesoille. « Monitoring of Radioactive Waste Disposal Cells in Deep Geological Formation ». Dans Supervision and Safety of Complex Systems, 7–12. Hoboken, NJ, USA : John Wiley & Sons, Inc., 2013. http://dx.doi.org/10.1002/9781118561744.ch2.

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Anikolenko, V. A., et V. A. Mansurov. « Kinetic Concept of Monitoring the Long-Term Stability of a Deep Repository for Radioactive Waste ». Dans Defence Nuclear Waste Disposal in Russia : International Perspective, 177–83. Dordrecht : Springer Netherlands, 1998. http://dx.doi.org/10.1007/978-94-011-5112-2_15.

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Verma, Amit Kumar, Pradeep Gautam, T. N. Singh et R. K. Bajpai. « Numerical Simulation of High Level Radioactive Waste for Disposal in Deep Underground Tunnel ». Dans Engineering Geology for Society and Territory - Volume 1, 499–504. Cham : Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-09300-0_94.

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Mansurov, V. A., et V. A. Anikolenko. « Acoustic Emission Monitoring : A Tool for the Selection and Nondestructive Characterization of Sites for the Deep Disposal of Radioactive Waste ». Dans Defence Nuclear Waste Disposal in Russia : International Perspective, 169–76. Dordrecht : Springer Netherlands, 1998. http://dx.doi.org/10.1007/978-94-011-5112-2_14.

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Actes de conférences sur le sujet "Deep disposal of radioactive waste"

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Ojovan, Michael I., Pavel P. Poluektov et Vladimir A. Kascheev. « Self-Disposal Option for Heat-Generating Waste ». Dans ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59182.

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Self-descending heat generating capsules can be used for disposal of dangerous radioactive wastes in extremely deep layers of the Earth preventing any release of radionuclides into the biosphere. Self-disposal option for heat-generating radioactive waste such as spent fuel, high level reprocessing waste or spent sealed radioactive sources, known also as rock melting concept, was considered in the 70s as a viable alternative disposal option by both Department of Energy in the USA and Atomic Industry Ministry in the USSR. Self-disposal is currently reconsidered as a potential alternative route to existing options for solving the nuclear waste problem and is associated with the renaissance of nuclear industry. Self-disposal option utilises the heat generated by decaying radionuclides of radioactive waste inside a heavy and durable capsule to melt the rock on its way down. As the heat from radionuclides within the capsule partly melts the enclosing rock, the relatively low viscosity and density of the silicate melt allow the capsule to be displaced upwards past the heavier capsule as it sinks. Eventually the melt cools and solidifies (e.g. vitrifies or crystallizes), sealing the route along which the capsule passed. Descending or self-disposal continues until enough heat is generated by radionuclides to provide partial melting of surrounding rock. Estimates show that extreme depths of several tens and up to hundred km can be reached by capsules which could never be achieved by other techniques. Self-disposal does not require complex and expensive disposal facilities and provides a minimal footprint used only at operational stage. It has also an extremely high non-proliferation character and degree of safety. Utilisation of heat generated by relatively short-lived radionuclides diminishes the environmental uncertainties of self-disposal and increases the safety of this concept. Self-sinking heat-generating capsules could be launched from the bottom of the sea as well as from intermediate-depth or deep boreholes. Self-disposal can also be used with a novel purpose — to penetrate into the very deep Earth’s layers beneath the Moho’s discontinuity and to explore Earth interior.
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Schneider, Lutz R., Christel Herzog et Michael Viehweg. « Injection of Liquid Radioactive Waste Into Deep Geological Formations at the Final Waste Disposal Sites Tomsk and Krasnoyarsk ». Dans ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1046.

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Abstract A special procedure for final disposal of liquid radioactive waste (LLW, ILW, HLW) — injection into deep geological formations — was developed in the former USSR and employed since 1963. This procedure was practiced at the sites of the Research Institute for Reactor Engineering Dimitrovgrad and at radiochemical facilities in Tomsk-7 and Krasnoyarsk-26. The deposits (layers of sand, limestone) lie at depths below 200 m and are isolated from other ground water horizons and the surface by overlying layers with low permeability. At the Krasnoyarsk site a total of approx. 5 × 106 m3 of low- to high-level waste were disposed at depths of 180–280 m and 350–500 m; at the Tomsk site a total of approx. 3.7×107 m3 of liquid radwaste were disposed at depths of 180–280 m and 270–320 m. The EU-project for assessing the final disposal safety of the Tomsk and Krasnoyarsk sites resulted in the improvement of a database, the development of a generic assessment model for the injection sites, a site-specific model for the repositories, the assessment of the performance of the repositories and finally recommendations to safety authorities.
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Kokorev, O. N., A. G. Kesler, A. D. Istomin, M. D. Noskov et A. A. Cheglokov. « GEOECOLOGICAL FORECAST FOR THE OPERATION OF A DEEP DISPOSAL SITE FOR LIQUID RADIOACTIVE WASTE ». Dans All-Russian Youth Scientific Conference with the Participation of Foreign Scientists Trofimuk Readings - 2021. Novosibirsk State University, 2021. http://dx.doi.org/10.25205/978-5-4437-1251-2-160-163.

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This work of a specialized information support system for the management of a deep disposal site for liquid radioactive waste is presented. The system consists of geo-information, technological-information, geotechnological modeling and expert-analytical modules. The application of the information support system to improve the safety of deep disposal site of liquid radioactive waste is considered.
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Stefanova, Ira G. « Disposal of Spent Sealed Sources ». Dans ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4972.

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Novi Han Repository is the only existing repository in Bulgaria for the disposal of radioactive waste from nuclear applications in industry, medicine and research. The disposal vault for spent sealed sources is not designed for disposal of powerful 137Cs and 60Co sources. Long-lived waste from nuclear applications are also not allowed for disposal at Novi Han Repository. As an operator of Novi Han Repository the Institute for Nuclear Research and Nuclear Energy initiated a program, for assessment of the possible utilization of deep shaft Gabra for disposal of such waste. The results of the preliminary study are discussed.
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Swift, Peter N., et David C. Sassani. « DEEP GEOLOGIC DISPOSAL OF RADIOACTIVE WASTE : MULTIPLE OPTIONS FOR LONG-TERM ISOLATION ». Dans GSA Annual Meeting in Denver, Colorado, USA - 2016. Geological Society of America, 2016. http://dx.doi.org/10.1130/abs/2016am-286507.

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Sassani, David. « U.S. R&D PROGRAM ON DEEP GEOLOGIC DISPOSAL OF RADIOACTIVE WASTE ». Dans GSA Connects 2021 in Portland, Oregon. Geological Society of America, 2021. http://dx.doi.org/10.1130/abs/2021am-369380.

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Hoorelbeke, Jean-Michel, Joël Chupeau, Jean Loubrieu, Jean-Baptiste Poisson et Richard Poisson. « The Research in France on Disposal Concepts for High Level and Long Lived Radioactive Waste in Deep Clay Formation ». Dans ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1292.

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Abstract The 15 year research on high level and long lived radioactive waste disposal in deep geological formations is being carried out by the ANDRA within the framework of the 1991 law. The status of the research program corresponds to the sinking of the shafts of the Meuse/Haute-Marne Underground Research Laboratory in an argilite layer. A set of preliminary concepts associated to this argillite layer has been studied to help address the issues raised by the feasibility analysis of a potential repository with respect to safety objectives. These concepts deal with transuranic no heat emitting waste, high level vitrified waste and potentially disposed spent fuel. Provision is made for a high level of flexibility, in particular regarding the reversibility of the step by step disposal process. The architecture of the repository concepts distinguishes disposal zones dedicated respectively to transuranic (type B) waste, vitrified high level (type C) waste, UOX and MOX spent fuel (if the case arrises). Each zone is itself divided into modules. The modular design, which segregates the waste categories, guarantees in particular the flexibility of the repository to contend with potential variations in inventory or waste management modes. This makes it possible to study the feasibility of disposal of each type of waste, in an independent way from the others. For each disposal zone and waste category, current studies, including safety and cost analysis, enable to compare various design options of the disposal cells and modules, prior to selecting those which will be presented in 2005. The paper mentions research targets of the program aiming at answering major scientific and technological questions raised by the concepts. The next milestone of the research program is scheduled at the end of the year 2001. It aims at tuning the approach to be used to assess the feasibility of disposal by 2005. The design will progressively benefit from the research carried out in the Meuse/Haute Marne underground research laboratory and other fields: The resulting data make it possible to fit the models used to dimension the structures, especially in the 2002–2005 period.
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Yoshikawa, Hidekazu. « A Proposal on Ultimate Safety Disposal of High Level Radioactive Wastes ». Dans 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15117.

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The ultimate disposal of high-level radioactive waste (HLW) becomes a hard issue for sustainable nuclear energy in Japan especially after Fukushima Daiichi accident. In this paper, the difficulty of realizing underground HLW disposal in Japanese islands is first discussed from socio-political aspects. Then, revival of old idea of deep seabed disposal of HLW in Pacific Ocean is proposed as an alternative way of HLW disposal. Although this had been abandoned in the past for the reason that it will violate London Convention which prohibits dumping radioactive wastes in public sea, the author will stress the merit of seabed disposal of HLW deep in Pacific Ocean not only from the view point of more safe and ultimate way of disposing HLWs (both vitrified and spent fuel) than by underground disposal, but also the emergence of new marine project by synergetic collaboration of rare-earth resource exploration from the deep sea floor in Pacific Ocean.
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Woller, Frantisek, et Lumir Nachmilner. « Reversibility and Retrievability Principles in the Czech Disposal Concept ». Dans ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1295.

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Abstract Reversibility and retrievability are topics that have recently been intensively discussed both within different national programs and at several international waste management events. While reversibility is a technical, iterative tool allowing optimization of the process of deep repository development, retrievability is considered to be a more political issue, a statute for which is not included in Czech legislation. However, both principles have been more or less incorporated into geological repository development and have also been considered as options for existing sub-surface repositories for institutional wastes. This paper summarizes Czech approaches to these issues.
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Rowat, John. « Safety and Sustainability Implications of Long Term Storage of Radioactive Waste ». Dans ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4548.

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Storage and disposal of radioactive waste are complementary rather than competing activities, and both are required for the safe management of wastes. Storage has been carried out safely within the past few decades, and there is a high degree of confidence that it can be continued safely for limited periods of time. However, as the amounts of radioactive waste in surface storage have increased, concern has grown over the sustainability of storage in the long term and the associated safety and security implications. In response to these concerns, the IAEA has prepared a position paper [1] that is intended for general readership. This presentation will provide a summary of the position paper, and a discussion of some safety issues for further consideration. A key theme is the contrast of the safety and sustainability implications of long term storage with those of early disposal. A number of factors are examined from different points of view, factors such as safety and security, need of maintenance, institutional control and information transfer, community attitudes and availability of funding. The timing and duration of the process of moving from storage to disposal, which are influenced by factors such as the long timeframes required to implement disposal and changing public attitudes, will also be discussed. The position paper focuses on the storage of three main types of waste: high level waste from the reprocessing of nuclear fuel, spent nuclear fuel that is regarded as waste and long-lived intermediate level radioactive waste. Long term storage of mining and milling waste, and other large volumes of waste from processes involving the use of naturally occurring radioactive materials are not discussed. Specialist meetings were held last year by the IAEA on the sustainability and safety of long-term storage to establish and discuss the issues where a broad consensus exists, and to investigate areas where issues remain unresolved. Within the technical community, it is widely agreed that perpetual storage is not considered to be either feasible or acceptable because of the impossibility of assuring active control over the time periods for which these wastes remain potentially hazardous. For high-level and long-lived radioactive waste, the consensus of the waste management experts is that disposal in deep underground engineered facilities — geological disposal — is the best option that is currently available, or likely to be available in the foreseeable future.
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Rapports d'organisations sur le sujet "Deep disposal of radioactive waste"

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Stein, Joshua S., Geoffrey A. Freeze, Patrick Vane Brady, Peter N. Swift, Robert Paul Rechard, Bill Walter Arnold, Joseph F. Kanney et Stephen J. Bauer. Deep borehole disposal of high-level radioactive waste. Office of Scientific and Technical Information (OSTI), juillet 2009. http://dx.doi.org/10.2172/985495.

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Herrick, Courtney Grant, Patrick Vane Brady, Steven Pye, Bill Walter Arnold, John Travis Finger et Stephen J. Bauer. Reference design and operations for deep borehole disposal of high-level radioactive waste. Office of Scientific and Technical Information (OSTI), octobre 2011. http://dx.doi.org/10.2172/1029790.

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Swift, Peter. Considerations of human inturison in U.S. programs for deep geologic disposal of radioactive waste. Office of Scientific and Technical Information (OSTI), janvier 2013. http://dx.doi.org/10.2172/1088098.

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Hadgu, Teklu, Emily Stein, Ernest Hardin, Geoffrey A. Freeze et Glenn Edward Hammond. Thermal-Hydrology Simulations of Disposal of High-Level Radioactive Waste in a Single Deep Borehole. Office of Scientific and Technical Information (OSTI), novembre 2015. http://dx.doi.org/10.2172/1226789.

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Gray, Genetha, Patrick Brady et Bill Arnold. Some logistical considerations in designing a system of deep boreholes for disposal of high-level radioactive waste. Office of Scientific and Technical Information (OSTI), septembre 2012. http://dx.doi.org/10.2172/1090212.

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Van Hoesen, S. (Low-level radioactive waste disposal). Office of Scientific and Technical Information (OSTI), juin 1985. http://dx.doi.org/10.2172/5273682.

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Brady, Patrick Vane, Bill Walter Arnold, Susan Jeanne Altman et Palmer Vaughn. Deep borehole disposal of nuclear waste summary. Office of Scientific and Technical Information (OSTI), septembre 2012. http://dx.doi.org/10.2172/1055644.

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White, G. J., T. W. Ferns, M. D. Otis, S. T. Marts, M. S. DeHaan, R. G. Schwaller et G. J. White. Low-level radioactive waste disposal facility closure. Office of Scientific and Technical Information (OSTI), novembre 1990. http://dx.doi.org/10.2172/6324264.

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Su, Jiann Cherng, et Ernest L. Hardin. Conceptual waste packaging options for deep borehole disposal. Office of Scientific and Technical Information (OSTI), juillet 2015. http://dx.doi.org/10.2172/1222453.

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Cranwell, R. M., J. E. Campbell, N. R. Ortiz et R. V. Guzowski. Risk methodology for geologic disposal of radioactive waste. Office of Scientific and Technical Information (OSTI), avril 1990. http://dx.doi.org/10.2172/7178896.

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