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Liu, Jie, Fang Xin Wei und Zhuo Wang. „Environmental Risk of Nuclear Power and Policy Proposal on Disposal of Solid Radioactive Waste“. Advanced Materials Research 726-731 (August 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 (06.06.2016): 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 und Hefin Griffiths. „The State of the Science and Technology in Deep Borehole Disposal of Nuclear Waste“. Energies 13, Nr. 4 (14.02.2020): 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, Nr. 4(98) (22.12.2020): 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, Nr. 1 (März 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 und Sokhee P. Jung. „Global Radioactive Waste Disposal Trends and Prospects“. Journal of Korean Society of Environmental Engineers 45, Nr. 4 (30.04.2023): 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 und T. M. Beattie. „Towards an 'implementing geological disposal technology platform' in Europe“. Mineralogical Magazine 76, Nr. 8 (Dezember 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 und John Apps. „Disposal of High-Level Nuclear Waste in Deep Horizontal Drillholes“. Energies 12, Nr. 11 (29.05.2019): 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, Nr. 5 (01.01.2007): 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 und Stephan Kurth. „Alternative Disposal Options for High-Level Radioactive Waste“. Safety of Nuclear Waste Disposal 1 (10.11.2021): 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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Tantau, Adrian, und Greta-Marilena Vitioanu. „Key factors affecting disposal of radioactive waste in the sustainable development approach“. Proceedings of the International Conference on Business Excellence 14, Nr. 1 (01.07.2020): 1–15. http://dx.doi.org/10.2478/picbe-2020-0002.
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AbstractThe radioactive waste disposal is a well investigated issue worldwide because of its importance for a safe and sustainable use of nuclear energy. Such waste is subject to final storage in deep geological disposals. Many factors have a direct contribution to the success of such innovative facility. The objective of the study is to identify the principal factors which contribute to the radioactive waste location. Factors that influence public acceptance are recognized and emphasized in the paper. The methodology is based on a questionnaire for empirical data obtaining and interviews with a selected group of experts to explore the insights of a disputed topic. The study reveals the quantitative analysis of the key factors as well-established contributors for understanding how and where to construct a radioactive waste facility. General information about the respondents was considered, as well as the possibility and the level of cooperation with stakeholders, the degree of information and the motivation of the given benefits as important influential factors over location and construction of a radioactive waste disposal. Overall, the study has shown that various factors influence the general public attitude, and this aspect leads to a direct influence on the location and construction of such a facility. The novelty of the research consists in key factors investigation that specially influence the location and the construction of a radioactive waste disposal, especially because the available literature studies in this area are not so strong developed yet.
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Swift, Peter N. „Climatic change and deep geologic disposal of radioactive waste“. Climatic Change 33, Nr. 3 (Juli 1996): 337–41. http://dx.doi.org/10.1007/bf00142581.
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Chen, Xiao Ming, Jie Zhu, Wei He und Xue Gang Luo. „Outline of Research on Interactions between Microorganisms and Geological Disposal of High-Level Radioactive Waste“. Advanced Materials Research 610-613 (Dezember 2012): 2282–86. http://dx.doi.org/10.4028/www.scientific.net/amr.610-613.2282.
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At present, in the geological disposal domain of high-level radioactive waste, little is known about microorganisms in deep underground geological environment in our country. This paper introduces some interactions between microbiological and geological disposal of high-level radioactive waste. There is a huge biosphere in the deep underground, mainly held by extremophiles. Microorganisms can influence the waste geological disposal environment in two aspects. On the one hand, the storehouse security will be confronted with serious problems of microorganisms because of their material corrosion capability. The main species of corrosion microorganisms include sulfate reducing bacteria, sulfur-oxidizing bacteria, saprophytic bacteria, iron bacteria and fungi. About research development on interactions between microbiological and geological disposal of high-level radioactive waste in China and abroad, foreign countries started early. Specialized research field has been formed and many achievements has been made by a series of research in Sweden, US, France, Canada, and so on. But relevant study is very few in our country. Therefore, there are special necessity and urgency to carry out this research.
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Melikhova, E. M., und E. О. Kuznetsova. „On the Public Acceptance of Deep Geological Repository Development in the Krasnoyarsk Region“. Radioactive Waste 25, Nr. 4 (2023): 23–34. http://dx.doi.org/10.25283/2587-9707-2023-4-23-34.
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The paper considers the issues associated with sustainable public acceptance of an ultra-long-term project on the development of a radioactive waste deep disposal facility in the Krasnoyarsk Region. It discusses the findings of a nationwide online survey focused radioactive waste disposal and the perception of relevant radiation hazards. The paper explores the deep roots causing inadequate public perception of radiation risks, as well as the disappointing results of many-year informative campaigns and the ICRP's enhanced approach to public dialogue as a possible way out of this communication impasse.
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Martynov, K. V., und A. N. Nekrasov. „Final Deep RW Disposal Facility: Petrography of the Site“. Radioactive Waste 28, Nr. 3 (2024): 59–75. http://dx.doi.org/10.25283/2587-9707-2024-3-59-75.
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Scanning electron microscopy with electron probe microanalysis has been used to study the main rock varieties of the Yeniseisky site (Krasnoyarsk Territory), where construction of an underground research laboratory has begun, as the first stage of the construction of a deep geological repository for radioactive waste. The petrographic typology of the studied rock samples is justified by their textural and structural characteristics, the main parageneses and the composition of rock-forming minerals, which are determined by the genesis of rocks. The results obtained can be used to substantiate the safety of the radioactive waste disposal facility to clarify the geological and structural models of the rock mass and the physicochemical conditions for the spread of radiation pollution as a result of the mobilization and transfer of radionuclides with pore-fractured groundwater.
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Van Geet, M., M. De Craen, D. Mallants, I. Wemaere, L. Wouters und W. Cool. „How to treat climate evolution in the assessment of the long-term safety of disposal facilities for radioactive waste: examples from Belgium“. Climate of the Past Discussions 5, Nr. 1 (13.02.2009): 463–94. http://dx.doi.org/10.5194/cpd-5-463-2009.
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Abstract. In order to protect man and the environment, long-lasting, passive solutions are needed for the different categories of radioactive waste. In Belgium, three main categories of conditioned radioactive waste (termed A, B and C) are defined by radiological and thermal power criteria. It is expected that Category A waste – low and intermediate level short-lived waste – will be disposed in a near-surface facility, whereas Category B and C wastes – high-level and other long-lived radioactive waste – will be disposed in a deep geological repository. In both cases, the long-term safety of a given disposal facility is evaluated. Different scenarios and assessment cases are developed illustrating the range of possibilities for the evolution and performance of a disposal system without trying to predict its precise behaviour. Within these scenarios, the evolution of the climate will play a major role as the time scales of the evaluation and long term climate evolution overlap. In case of a near-surface facility (Category A waste), ONDRAF/NIRAS is considering the conclusions of the IPCC, demonstrating that a global warming is nearly unavoidable. The consequences of such a global warming and the longer term evolutions on the evolution of the near-surface facility are considered. In case of a geological repository, in which much longer time frames are considered, even larger uncertainties exist in the various climate models. Therefore, the robustness of the geological disposal system towards the possible results of a spectrum of potential climate changes and their time of occurrence will be evaluated. The results of climate modelling and knowledge of past climate changes will merely be used as guidance of the extremes of climate changes to be considered and their consequences.
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Bharath Kumar T und Lingaraju M P. „Nuclear waste management: Innovative techniques for long-term storage“. World Journal of Advanced Research and Reviews 3, Nr. 2 (30.09.2019): 136–46. https://doi.org/10.30574/wjarr.2019.3.2.0114.
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Nuclear waste management remains a critical challenge in the field of nuclear energy, requiring advanced solutions to ensure the safe, long-term disposal of radioactive materials. The proper handling and containment of nuclear waste are essential to minimizing environmental risks and ensuring public safety. This paper explores innovative techniques for the long-term storage and disposal of nuclear waste, focusing on three key areas: deep geological repositories, advanced vitrification processes, and novel containment materials. Deep geological repositories provide a secure and stable underground environment for isolating high-level radioactive waste, reducing the risk of surface contamination. Advanced vitrification processes enhance the immobilization of radioactive elements by incorporating them into stable glass matrices, improving durability and resistance to leaching. Additionally, novel containment materials, such as advanced ceramic and composite materials, offer enhanced structural integrity and radiation shielding properties for long-term storage solutions. Furthermore, this study presents a comprehensive analysis of statistical data, figures, and bar charts to evaluate the effectiveness and reliability of these nuclear waste management strategies. By comparing various disposal techniques, this research aims to highlight the most promising advancements in the field and provide insights into future directions for safe and sustainable nuclear waste disposal. The findings underscore the importance of continued research and technological innovation in developing robust nuclear waste management solutions that align with global environmental and safety regulations.
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Gibb, Fergus G. F., und A. John Beswick. „A deep borehole disposal solution for the UK's high-level radioactive waste“. Proceedings of the Institution of Civil Engineers - Energy 175, Nr. 1 (Februar 2022): 11–29. http://dx.doi.org/10.1680/jener.21.00015.
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The size of deep boreholes suitable for disposal of radioactive wastes can be increased through an innovative combination of blind shaft and oilfield drilling technologies. This would enable deep borehole disposal (DBD) of the UK's high-level waste (HLW), which is being packaged in containers hitherto considered too large for DBD and destined for a deep geological repository (DGR/GDF). DBD could advance, by over 40 years, disposal of this waste, avoid expensive replacement of ageing storage facilities and reduce the size and cost of the DGR/GDF by up to 70%. A generic reference design is presented for the boreholes and a route proposed for DBD of the UK's HLW in between seven and ten boreholes on a site smaller than three football pitches. Following location and approval of a suitable site, disposal could be completed in under 10 years using currently available technology. Estimates are presented that show the entire programme, including a non-active demonstration borehole, could be undertaken for less than £744 million (at today's prices); a saving of over £8.5 billion on the estimated cost of the proposed DGR/GDF. Implementing DBD of the UK's HLW could begin now and should be reconsidered as a matter of urgency.
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Sookhak Lari, Kaveh, und Dirk Mallants. „Coupled Heat-Mass Transport Modelling of Radionuclide Migration from a Nuclear Waste Disposal Borehole“. Geofluids 2022 (04.04.2022): 1–23. http://dx.doi.org/10.1155/2022/5264257.
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Disposal of radioactive waste originating from reprocessing of spent research reactor fuel typically includes stainless steel canisters with waste immobilised in a glass matrix. In a deep borehole disposal concept, waste packages could be stacked in a disposal zone at a depth of one to potentially several kilometres. This waste will generate heat for several hundreds of years. The influence of combining a natural geothermal gradient with heat from decaying nuclear waste on radionuclide transport from deep disposal boreholes is studied by implementing a coupled heat-solute mass transport modelling framework, subjected to depth-dependent temperature, pressure, and viscosity profiles. Several scenarios of waste-driven heat loads were investigated to test to what degree, if any, the additional heat affects radionuclide migration by generating convection-driven transport. Results show that the heat output and the calculated radioactivity at a hypothetical near-surface observation point are directly correlated; however, the overall impact of convection-driven transport is small due to the short duration (a few hundred years) of the heat load. Results further showed that the calculated radiation dose at the observation point was very sensitive to the magnitude of the effective diffusion parameter of the host rock. Coupled heat-solute mass transport models are necessary tools to identify influential processes regarding deep borehole disposal of heat-generating long-lived radioactive waste.
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Chapman, Neil. „Who Might Be Interested in a Deep Borehole Disposal Facility for Their Radioactive Waste?“ Energies 12, Nr. 8 (24.04.2019): 1542. http://dx.doi.org/10.3390/en12081542.
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The deep borehole disposal (DBD) concept for certain types of radioactive wastes has been discussed for many decades, but has enjoyed limited R&D interest compared to ‘conventional’ geological disposal in an excavated repository at a few hundreds of metres depth. This article explores the circumstances under which a national waste management programme might wish to consider DBD. Starting with an assumption that further R&D will answer technical issues of DBD feasibility, it examines the types of waste that might be routed to borehole disposal and the strategic drivers that might make DBD attractive. The article concludes by identifying the types of national programme that might wish to pursue DBD further and the pre-requisites for them to give it serious consideration.
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Bamborin, M. Yu, V. V. Martyanov, A. N. Kamanin und A. V. Minin. „Efficient Use of Licensed Subsurface Sites in the Management of Liquid Radioactive Waste During Its Geological Disposal“. Radioactive Waste 22, Nr. 1 (2023): 23–27. http://dx.doi.org/10.25283/2587-9707-2023-1-23-27.
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The paper considers the structure of a deep disposal facility for liquid radioactive waste, the diagram of liquid radioactive waste spread within the mining allotment, and technical solutions enabling filtration flow redistribution through the use of barrage injection and extraction wells or observation and backup wells to provide long-term safe operation of the facility.
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Rafat, G., S. Bissmann, B. Lehmann, B. Dombrowski und A. Yu Vedyaev. „ENERGY OF DEEP GEOTHERMAL DEPOSITS AND RADIOACTIVE WASTE FINAL DISPOSAL“. Occupational Safety in Industry, Nr. 12 (Dezember 2018): 7–15. http://dx.doi.org/10.24000/0409-2961-2018-12-7-15.
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Dorofeev, A. N., A. V. Ponizov, A. I. Rybalchenko, E. V. Zakcharova, A. A. Zubkov, P. M. Vereshchagin, A. L. Vasilishin et al. „Results of Computational and Experimental Studies on the Long-Term Safety Justification of Deep Disposal Facilities for LRW“. Radioactive Waste 21, Nr. 4 (2022): 24–38. http://dx.doi.org/10.25283/2587-9707-2022-4-24-38.
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The article overviews the findings of individual studies under the Program of Calculation and Experimental Research Seeking to Demonstrate and Assess the Long-term Safety of Deep Disposal Facilities for Liquid Radioactive Waste Aiming to Implement the Recommendations of the IAEA Peer Review of the Deep Well Injection Practice for Liquid Radioactive Waste in the Russian Federation. To demonstrate the long-term safety of the Zheleznogorsk, Seversk and Dimitrovgrad deep disposal facilities for liquid radioactive waste (hereinafter referred to as the DDF LRW), data on the geological and hydrogeological conditions in the regions and at the DDF LRW sites were collected and systematized; the processes occurring in DDF LRW near and far zones, including those involved in radioactive waste (RW) component transport, were studied; evolution scenarios for the RW disposal system were developed, including a forecast describing potential climate changes in the DDF LRW areas covering a period of up to 100,000 years; conceptual and mathematical DDF LRW models were developed; computer software was used in predictive calculations focused on the migration of liquid RW components in the operational DDF LRW horizons with the potential radiation impact on the population been assessed. The study also involved some computational and experimental research focused on the evolution of backfill materials to develop the designs of some additional engineered safety barriers to be installed during DDF LRW DGR well abandonment; the paper also presents the approaches to the development of the DDF LRW closure concept.
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Ojovan, Michael I. „Challenges in the Long-Term Behaviour of Highly Radioactive Materials“. Sustainability 14, Nr. 4 (21.02.2022): 2445. http://dx.doi.org/10.3390/su14042445.
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Highly radioactive materials are at the core in many useful applications ranging from operating nuclear reactors (including fast breeder reactors) to vitrified high-level radioactive waste, which is currently stored and awaiting final disposal into dedicated facilities within deep geological formations [...]
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Linge, I. I. „Streamlining RW management and radiation safety systems“. Radioactive Waste 23, Nr. 2 (2023): 21–34. http://dx.doi.org/10.25283/2587-9707-2023-2-21-34.
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The paper discusses the issues associated with the segregation of the radiation safety and RW management systems. It highlights the need for further upgrading of regulations and methodological provisions establishing the rules for waste categorization as radioactive as it comes to the lists of radionuclides and the numerical values involved; radioactive waste categorization as non-removable waste, identification of the potential hazard periods, selection of decommissioning strategies with the focus placed on the priority radionuclides. The study demonstrates that considering all spent nuclear fuel reprocessing scenarios no alternative can be proposed to the deep radioactive waste disposal option.
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Carpén, Leena, Pauliina Rajala und Malin Bomberg. „Microbially Induced Corrosion in Deep Bedrock“. Advanced Materials Research 1130 (November 2015): 75–78. http://dx.doi.org/10.4028/www.scientific.net/amr.1130.75.
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This paper covers an overview of recent research of microbially induced corrosion in Fennoscandian terrestrial deep bedrock groundwater environment. The assessment of microbially induced corrosion of metals in the deep bedrock environment has become important in evaluating the long-term safety of disposal of radioactive waste.
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Chen, Wenzhen, Jianli Hao und Zhiyun Chen. „A Study of Self-Burial of a Radioactive Waste Container by Deep Rock Melting“. Science and Technology of Nuclear Installations 2013 (2013): 1–6. http://dx.doi.org/10.1155/2013/184757.
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Aiming at the problem of radioactive waste disposal, the concept and mechanism of self-burial by deep rock melting are presented. The rationality and feasibility of self-burial by deep rock melting are analyzed by comparing with deep geological burial. The heat threshold during the process of contact melting around a spherical heat source is defined. The descent velocities and burial depths of spherical waste containers with varying radius are calculated. The calculated depth is much smaller than that obtained in the related literature. The scheme is compared with the deep geological burial that is currently carried out by the main nuclear countries. It is found that, at the end of melting, a radioactive waste container can reach deep strata that are isolated from groundwater.
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Алой, А. С., Н. В. Ковалёв, А. М. Прокошин, А. И. Блохин, П. А. Блохин, А. В. Курындин, А. В. Понизов und С. В. Маковский. „ON THE EVALUATION OF ABSORBED DOSE IN VITRIFIED HIGH LEVEL RADIOACTIVE WASTE WITH THE ACCOUNT OF REAL CAN GEOMETRY“. ЯДЕРНАЯ И РАДИАЦИОННАЯ БЕЗОПАСНОСТЬ, Nr. 4(98) (22.12.2020): 61–72. http://dx.doi.org/10.26277/secnrs.2020.98.4.006.
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При переработке отработавшего ядерного топлива образуется существенное количество радиоактивных отходов, большая часть из которых подлежит локализации в стеклоподобном компаунде и последующему захоронению в геологических формациях. Одним из основных требований к компаунду отходов является его длительная радиационная стойкость под действием излучения от включенных в матрицу радионуклидов. Для подтверждения радиационной стойкости должна быть определена величина дозы, поглощаемой в объеме матрицы после момента остекловывания. В настоящей работе представлены результаты расчетного моделирования набора поглощенной дозы в высокоактивных отходах, остеклованных в боросиликатную матрицу, при их долговременном хранении и последующем захоронении. A large amount of radioactive waste is produced during reprocessing of spent nuclear fuel. Most of this radioactive waste is subject to vitrification in glass-like compound and to subsequent deep geological disposal. One of the main requirements to radioactive waste compound is radiological stability under radiation of nuclides in waste for a long period of time.An amount of absorbed dose in compound volume shall be determined in order to justify radiological stability of radioactive waste. This article presents the results of absorbed dose calculation in radioactive waste in borsilicate glass matrix during long-term storage and subsequent disposal.
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Martynov, K. V., und E. V. Zakharova. „Leaching Factors for a Phosphate Radioactive Waste form Under Deep Disposal Conditions“. Radioactive Waste 23, Nr. 2 (2023): 63–81. http://dx.doi.org/10.25283/2587-9707-2023-2-63-81.
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The article presents the results of experiments on the interaction of model phosphate waste form materials of various phase compositions containing simulators of RW elements with leaching solutions simulating groundwater and changes in its composition due to the impact produced by bentonite barrier material, radiolysis and alkaline plume from Portland cement concrete at temperatures of 25, 90 and 120°С under static water mode considered typical for deep RW disposal facilities. It provides numerical data on the equilibrium saturation concentrations of leaching solutions saturated with barrier and waste form components and simulators of RW elements during phosphate waste form leaching. The paper also discusses the degree of influence produced by the main leaching factors (the phase waste form composition, elevated temperature, the consequences of radiolysis and groundwater interaction with barrier and structural materials) on the concentrations of elements in RW phosphate waste form leachates under the disposal conditions.
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Morozov, Vladislav, Victor Tatarinov, Ilya Kolesnikov, Alexander Kagan und Tatiana Tatarinova. „Tectonic Processes Modeling For High-Level Radioactive Waste Disposal“. Environment. Technology. Resources. Proceedings of the International Scientific and Practical Conference 1 (05.08.2015): 9. http://dx.doi.org/10.17770/etr2011vol1.910.
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The possibility of using deep geological formations to dispose of high-level radioactive waste (HLW) is a subject raising heated debate among scientists. In Russia, the idea of constructing HLW repository in the Niznekansky granitoid massif (NKM) in Krasnoyarsk area is widely discussed. To solve this problem we are elaborating a technology associated with time – space stability prediction of the geological environment, which is subject to geodynamic processes evolutionary effects. It is based on the prediction of isolation properties stability in a structural tectonic block of the Earth’s crust for a given time. The danger is in the possibility that the selected structural block may be broken by new tectonic faults or movements on a passive fault may be activated and thus underground water may penetrate to HLW containers.
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Abramova, Elena, Natalia Shapagina, Grigoriy Artemiev und Alexey Safonov. „Microbial Corrosion of Copper Under Conditions Simulating Deep Radioactive Waste Disposal“. Biology 13, Nr. 12 (23.12.2024): 1086. https://doi.org/10.3390/biology13121086.
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This paper presents the results of microbial corrosion tests on M0-grade copper under conditions simulating a geological repository for radioactive waste at the Yeniseisky site (Krasnoyarsk Krai, Russia). The work used a microbial community sampled from a depth of 450 m and stimulated with glucose, hydrogen and sulfate under anaerobic conditions. It was shown that the maximum corrosion rate, reaching 9.8 µm/y, was achieved with the addition of sulfate (1 g/L) with the participation of microorganisms from the families Desulfomicrobiaceae, Desulfovibrionaceae and Desulfuromonadaceae. It was noted that the most important factor leading to copper corrosion was the accumulation of hydrogen sulfide during the activation of sulfate-reducing microorganisms of the genera Desulfomicrobium, Desulfovibrio and Desulfuromonas. During the development of the microbial community under these conditions, the content of copper can have a significant toxic effect at a concentration of more than 250 mg/L.
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Hipkins, E. V., R. S. Haszeldine und C. I. McDermott. „Comparing the prospectivity of hydrogeological settings for deep radioactive waste disposal“. Hydrogeology Journal 28, Nr. 6 (15.06.2020): 2241–57. http://dx.doi.org/10.1007/s10040-020-02182-2.
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Abstract Nuclear power has the potential to provide significant amounts of reliable electricity generation without carbon dioxide emissions. Disposing of radioactive waste is, however, an ongoing challenge, and if it is to be buried, the characterisation of the regional groundwater system is vital to protect the anthroposphere. This aspect is understudied in comparison to the engineered facility; yet, selecting a suitable groundwater setting can ensure radionuclide isolation hundreds of thousands of years beyond that provided by the engineered structure. This paper presents a multi-faceted scoping tool to quantitatively assess, and directly compare, the regional hydrogeological prospectivity of different groundwater settings for disposal at an early stage of the site selection process. The scoping tool is demonstrated using geological data from three distinct UK groundwater settings as a case study. Results indicate a significant difference in the performance potential of different regional groundwater settings to ensure long-term waste containment.
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Levizzari, Riccardo, Barbara Ferrucci und Alfredo Luce. „Preliminary analysis of gaseous radiocarbon behavior in a geological repository hosted in salt rock“. Radiocarbon 60, Nr. 6 (29.11.2018): 1897–910. http://dx.doi.org/10.1017/rdc.2018.133.
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ABSTRACTA preliminary evaluation of gaseous radiocarbon (14C) behavior under geological repository conditions for Italian radioactive high level waste-long-lived and intermediate level waste disposal has been performed. Although in Italy there is still no defined project for a geological disposal facility, current work may support future safety assessment studies for a hypothetical future repository in deep salt rock. In the Italian context of radioactive waste, the percentage of 14C bearing waste to be disposed in a possible geological repository is low; irradiated graphite is the most important radiological source. Data about the radiological inventory has been collected to simulate production and migration of gaseous 14C in a hypothetical geological repository. Three different conceptual models have been developed and simulated. The first model has considered a preliminary evaluation of the radiological impact referred to the whole inventory; the second and third model have evaluated the impact only due to the irradiated graphite. A preliminary sensitivity analysis has been carried out, highlighting the importance of geometry and of distribution coefficients (Kd) in materials used to seal the disposal underground facility. Results show the possibility to correlate the Kd values, the volume and the location of the sealing materials to the amount of 14C migrating toward the surface.
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Havlova, Vaclava, Stefan Mayer und Paul Degnan. „International Atomic Energy Agency (IAEA) support for the management of site investigations for radioactive waste disposal facilities“. Safety of Nuclear Waste Disposal 2 (06.09.2023): 35–36. http://dx.doi.org/10.5194/sand-2-35-2023.
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Abstract. Providing safe, secure and environmentally acceptable radioactive waste disposal is a national responsibility that requires a long-term commitment, adequate resources and the involvement of multiple stakeholders. The choice of a particular disposal concept and its detailed design will depend on several factors, such as the properties of the waste inventory to be disposed of, national circumstances and strategic preferences. A concept is likely to evolve iteratively as one or more sites are investigated and the repository design is refined to reflect local conditions. In this context, the International Atomic Energy Agency (IAEA) recently published technical guidance on the management of site investigations for radioactive waste repositories. A key objective of the publication Management of Site Investigations for Radioactive Waste Disposal Facilities (IAEA, 2023) is to ensure that site investigation efforts in Member states have firm foundations based on a clear understanding of data and information requirements. The publication was developed to reflect the experiences and knowledge from a range of disposal programmes, and it is intended to support initiation of well-planned and focused site investigations in Member states with a need to develop and site radioactive waste disposal facilities. A siting process is intended to result in the identification of a suitable location for any nuclear installation, including a deep geological repository, and ultimately to receive authorisation to construct and operate the facility. To achieve this objective, it will be necessary to ensure that the combination of site properties and engineered barrier properties provides requisite levels of safety for the inventory under consideration (IAEA, 2015). The siting process and associated site investigations for a radioactive waste disposal facility follow a stepwise process, irrespective of whether the early stages of siting start with investigating and screening the national territory or whether the iterative investigation process starts with a more focused approach, e.g. volunteer sites, sites with already well-known characteristics, sites with existing nuclear facilities or similar ones (IAEA, 2023). Site investigations should follow a graded approach in an iterative manner, reflecting a phased approach to decision-making and the development of disposal facilities (IAEA, 2011). At each stage in the siting process the disposal system is to be evaluated based on the data and information available at that time. Following an assessment, a gap analysis comparing requirements to knowledge about the site would identify process model and data uncertainties affecting confidence in the implementation of the disposal concept at the site. Furthermore, the IAEA also recently launched a project to develop guidance reflecting good practices in Member states' programmes for establishing site selection criteria and applying a decision-making framework as part of a siting process.
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Kuzmin, E. V., A. V. Kalakutskiy, M. A. Tarasov und A. A. Morozov. „Concept for Disposal of Class 2 and Class 3 Radioactive Waste in Underground Workings with Isolating Backfilling using Paste made with Processed Uranium Ore Materials“. Mining Industry (Gornay Promishlennost), Nr. 6/2020 (29.12.2020): 31–36. http://dx.doi.org/10.30686/1609-9192-2020-6-31-36.
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The paper presents a concept for disposal of Class 2 and Class 3 radioactive waste in existing workings and chambers in the underground uranium mines of the Priargunsky Industrial Mining and Chemical Union PJSC with isolation of radioactive waste storage chambers using paste backfilling made with processed uranium ore materials and sealing of cracks in host rock by injection consolidation. The need is shown to enhance the strength of radioactive waste containers to increase the number of tiers in the storage blocks to make better use of the available chamber space. Data is provided on the forecast hydrogeological conditions in deep levels (up to 1000 m) of Mine No.6.
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Cho, Hye-Ryun, Young-Sang Youn, Euo Chang Jung und Wansik Cha. „Hydrolysis of trivalent plutonium and solubility of Pu(OH)3(am) under electrolytic reducing conditions“. Dalton Transactions 45, Nr. 48 (2016): 19449–57. http://dx.doi.org/10.1039/c6dt03992h.
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This paper focusses on the determination of the thermodynamic data of Pu(iii) hydrolysis, which are important for a long-term safety assessment of high-level radioactive waste disposal in a deep geological system.
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Boldyrev, K. A., D. A. Sobolev, B. T. Kochkin und A. S. Barinov. „Studies of natural and historical analogues and the use of their findings in the assessment of safety barrierbehavior under the safety demonstration of radioactive waste disposal facilities“. Radioactive Waste 20, Nr. 3 (2022): 72–96. http://dx.doi.org/10.25283/2587-9707-2022-3-72-96.
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The article discusses and substantiates the possibility and necessity of applying the findings of studies focused on natural and historical analogues in the development of radioactive waste disposal facilities (RWDF) and demonstration of their long-term safety. It explores the issues associated with the behavior of various structural materials used in the construction of RWDF, in particular, those used in the development of engineered safety barrier system (EBS). The article overviews available publications on natural and historical analogues of engineered barrier materials — silicate glasses, native and anthropogenic copper and bronze, iron, alkaline cements, uranium deposits, as well as the system of natural reactors in Oklo considered as an analogue of deep disposal facilities for radioactive waste. It evaluates natural conditions contributing to the preservation of their insulating properties and the containment of radionuclides contained in the radioactive waste (RW) in the system of engineered and natural RWDF barriers. The study concludes that the findings of the studies can and should be used to provide parametric support in computational modeling applied to assess the long-term safety of RW disposal systems.
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Suskin, V. V., I. V. Kapyrin und K. A. Boldyrev. „Near and Far Fields of a Radioactive Waste Disposal Facilities: Approaches to their Modeling Based on the GeRa Software“. Radioactive Waste 24, Nr. 3 (2023): 117–25. http://dx.doi.org/10.25283/2587-9707-2023-3-117-125.
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The study focuses on the safety assessment of near-surface radioactive waste disposal facilities (NSDF) based on the numerical simulation of radionuclide transport in the near field via groundwater flow and mass transport processes using the GeRa software. It also evaluates the methods that may provide near and far field model coupling seeking to arrange a sound safety assessment process. The study specifically focuses on the degradation of the underlying concrete safety barrier indicated through a reduced radionuclide absorption capacity. The study provides calculations for those radionuclides that are typically found in the radioactive waste subject to disposal in deep disposal facilities. The findings evidence some fundamental difference in the activity-yield curves associated with the sorption properties, changes in the barrier properties and the half-lifes of the modelled radionuclides.
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Bracke, Guido, Wolfram Kudla und Tino Rosenzweig. „Status of Deep Borehole Disposal of High-Level Radioactive Waste in Germany“. Energies 12, Nr. 13 (04.07.2019): 2580. http://dx.doi.org/10.3390/en12132580.
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The phase-out of nuclear energy in Germany will take place in 2022. A site for final disposal of high-level radioactive waste (HLRW) has not yet been chosen, but a site selection process was restarted by the Site Selection Act in 2017. This Act was based on a recommendation by a commission which also advised to follow up the development of deep borehole disposal (DBD) as a possible option for final disposal of HLRW. This paper describes briefly the status of DBD in Germany and if this option is to be pursued in Germany. Although DBD has some merits, it can only be a real option if supported by research and development. The technical equipment for larger boreholes of the required size will only be developed if there is funding and a feasibility test. Furthermore, any DBD concept must be detailed further, and some requirements of the Act must be reconsidered. Therefore, the support of DBD will likely remain at a low level if there are no political changes.
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Sorokin, V. T., R. M. Gataullin, N. V. Sviridov und D. I. Pavlov. „Durability of reinforced concrete containers NZK-150-1.5P during the disposal of radioactive waste class 2“. Radioactive Waste 20, Nr. 3 (2022): 37–49. http://dx.doi.org/10.25283/2587-9707-2022-3-37-49.
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The article focuses on experimental, calculation and analytical basis demonstrating the durability of reinforced concrete NZK-150-1.5P containers designed for the deep disposal of intermediate long-lived class 2 radioactive waste in the Nizhnekanskiy rock mass (DDFRW NKM) and the associated challenges. The article shows that the regulatory framework should be updated to reduce the requirements specifying the time during which the packages have to maintain their protective properties in case of intermediate-level waste class 2 disposal.
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Fernández, Ana María, Stephan Kaufhold, Markus Olin, Lian-Ge Zheng, Paul Wersin und James Wilson. „Editorial for Special Issue “Clay Mineral Transformations after Bentonite/Clayrocks and Heater/Water Interactions from Lab and Large-Scale Tests”“. Minerals 12, Nr. 5 (30.04.2022): 569. http://dx.doi.org/10.3390/min12050569.
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This Special Issue “Clay Mineral Transformations after Bentonite/Clayrocks and Heater/Water Interactions from Lab and Large-Scale Tests” covers a broad range of relevant and interesting topics related to deep geological disposal of nuclear fuels and radioactive waste [...]
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Линге, И. И., und С. С. Уткин. „DEEP DISPOSAL OF RADIOACTIVE WASTE IN THE CONTEXT OF THE RADIOEQUIVALENT APPROACH“. ЯДЕРНАЯ И РАДИАЦИОННАЯ БЕЗОПАСНОСТЬ, Nr. 2(108) (14.07.2023): 42–56. http://dx.doi.org/10.26277/secnrs.2023.108.2.003.
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Рассмотрены основные недостатки так называемого радиоэквивалентного подхода к захоронению радиоактивных отходов. На конкретных примерах выполнен анализ отказа от международно признанных методов и принципов обеспечения радиационной безопасности в пользу замены общепринятых операционных величин нефизичными функционалами от активности радиоактивных отходов и природного урана. В результате сопоставление получаемых результатов с фактическими и прогнозными данными, характеризующими реальную радиационную опасность обращения с отработавшим ядерным топливом и радиоактивными отходами, показало, что радиоэквивалентный подход не позволяет корректно сравнивать опасность различных вариантов топливных циклов и, более того, делать на этом основании выводы о преимуществах отдельных реакторных и радиохимических технологий. Причины, в частности, состоят в том, что: ▪ вместо сравнений выгод и затрат (вреда) сравниваются две компоненты вреда, связанные с опасностью извлекаемого урана и подлежащих захоронению радиоактивных отходов; ▪ сценарий определения потенциальной опасности добываемого урана и отработавшего ядерного топлива через поступление их в организм с водой и вдыхаемым воздухом приводит к завышению значений получаемых доз, в сравнении с подтвержденными практикой оценками, в миллиарды раз; ▪ не принимаются во внимание последствия имеющихся неопределенностей, а проблема наличия этих неопределенностей решается некорректно. Фактические данные убедительно подтверждают, что на протяжении всех лет существования атомной энергетики основные дозы облучения от деятельности объектов ядерного топливного цикла и АЭС были связаны с добычей урана. При этом дозы от добычи и транспортировки урана на порядок выше, чем фактические и прогнозируемые дозы от захоронения отработавшего ядерного топлива и радиоактивных отходов. The paper considers the main drawbacks of the radioequivalent (radiotoxicity) approach to the disposal of radioactive waste based on the analysis of the case studies of applications of this approach. The results of the comparison with actual and forecast data show that the rejection of internationally recognized radiation safety principles in favor of non-physical functionals of radioactive waste and natural uranium activities radioequivalent approach gives neither correct comparison of hazard of various fuel cycle options nor valid conclusions on the advantages of various reactor and radiochemical technologies. In particular, the reasons are as follows: - instead of comparison of benefits and costs (hazard), the comparison of the two components of the hazard is carried out related to uranium mining and radioactive waste disposal; - the scenario of evaluation of the potential hazards of the mined uranium and spent nuclear fuel via water intake and inhalation causes billion-fold overestimated exposure values compared to the practical evidence; - implications of existing uncertainties are not considered with the uncertainty management problem itself being addressed incorrectly. Actual data definitely confirm that throughout the nuclear power era, the major doses of radiation exposure from nuclear fuel cycle facilities and NPPs have been mainly associated with uranium mining. Exposure from uranium mining and transportation is several orders greater than the actual and forecasted doses from spent nuclear fuel and radioactive waste disposal.
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Thakur, P., J. Monk und J. L. Conca. „Environmental monitoring of radioactive and non-radioactive constituents in the vicinity of WIP“. Proceedings in Radiochemistry 1, Nr. 1 (01.09.2011): 269–76. http://dx.doi.org/10.1524/rcpr.2011.0047.
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Abstract The Waste Isolation Pilot Plant (WIPP), a US Department of Energy (DOE) facility, is a deep geologic transuranic waste disposal site designed for the safe disposal of transuranic (TRU) wastes generated from the US defense program. Monitoring is a key component of the development and operation of any nuclear repository and is important to the WIPP performance assessment. Initial concerns over the release of radioactive and chemical contaminants from the WIPP led to various monitoring programs, including the independent, academic-based WIPP environmental monitoring (WIPP-EM) program conducted by the New Mexico State University (NMSU) Carlsbad Environmental Monitoring and Research Center (CEMRC) located in Carlsbad, NM. The mission of CEMRC is to develop and implement an independent health and environmental monitoring program in the vicinity of WIPP and make the results easily accessible to the public and all interested parties. Under the WIPP-EM program constituents monitored include: (1) selected radionuclides, elements, and ions of interest in air, soil, vegetation, drinking water, surface water and sediment from within a 100-mile radius of WIPP as well as in the air exiting the WIPP exhaust shaft, and (2) internally deposited radionuclides in the citizenry living within a 100-mile radius of WIPP. This article presents an evaluation of more than tens years of environmental monitoring data that informed the public that there is no evidence of increases in radiological contaminants in the region that could be attributed to releases from the WIPP. Such an extensive monitoring program and constant public engagement is an ideal model for all nuclear waste repositories anywhere in the world.
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Rejková, Jana, Jan Macák und Lumír Nachmilner. „The Waste Disposal Package for Spent Nuclear Fuel“. Chemické listy 116, Nr. 2 (15.02.2022): 110–14. http://dx.doi.org/10.54779/chl20220110.
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A key issue in the safety of spent nuclear fuel storage is the lifetime and effectiveness of barriers isolating the radioactive waste from the environment. In the event of a failure of the waste disposal package, the condition of the fuel pellets and the impact on their immediate surroundings will be an important factor. The goal of this review article is to summarize the state and changes of nuclear fuel at the end of the fuel cycle and the influence of the parameters of the deep repository environment on the corrosion processes of the engineered barriers and on the release of radionuclides during storage.
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Husar, Richard, René Hübner, Christoph Hennig, Philippe M. Martin, Mélanie Chollet, Stephan Weiss, Thorsten Stumpf, Harald Zänker und Atsushi Ikeda-Ohno. „Intrinsic formation of nanocrystalline neptunium dioxide under neutral aqueous conditions relevant to deep geological repositories“. Chemical Communications 51, Nr. 7 (2015): 1301–4. http://dx.doi.org/10.1039/c4cc08103j.
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Simple dilution of an aqueous Np(iv) bicarbonate solution triggers the intrinsic formation of nanocrystalline neptunium dioxide (NpO2). This new formation route could be a likely scenario in the repository and disposal of radioactive waste.
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Walke, R. C., M. C. Thorne und S. Norris. „Biosphere studies supporting the disposal system safety case in the UK“. Mineralogical Magazine 76, Nr. 8 (Dezember 2012): 3225–32. http://dx.doi.org/10.1180/minmag.2012.076.8.35.
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AbstractHigher activity radioactive wastes remain hazardous for extremely long timescales, of up to hundreds of thousands of years. Disposing of such wastes deep underground presents the internationally accepted best solution for isolating them from the surface environment on associated timescales. Geological disposal programmes need to assess potential releases from such facilities on long timescales to inform siting and design decisions and to help build confidence that they will provide an adequate degree of safety. Assessments of geological disposal include consideration of the wastes, the engineered facility, the host geology and the surface and near-surface environment including the biosphere. This paper presents an overview of recent post-closure biosphere assessment studies undertaken in support of the Nuclear Decommissioning Authority Radioactive Waste Management Directorate disposal system safety case for geological disposal of the United Kingdom's higher activity radioactive wastes. Recent biosphere studies have included: (1) ensuring that the United Kingdom's approach to consideration of the biosphere in safety case studies continues to be fit for purpose, irrespective of which site or sites are considered in the United Kingdom's geological disposal programme; (2) updating projections of global climate and sea level, together with consideration of the potential importance of transitions between climate states; (3) considering geosphere–biosphere interface issues and their representation, including redox modelling and catchment-scale hydrological modelling; and (4) identifying key radionuclides and developing a series of reports describing their behaviour in the biosphere together with an evaluation of associated implications for post-closure assessment calculations.
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Park, Kyung-Woo, Kyung-Su Kim, Yong-Kwon Koh, Yeonguk Jo und Sung-Hoon Ji. „Review of Site Characterization Methodology for Deep Geological Disposal of Radioactive Waste“. Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) 15, Nr. 3 (30.09.2017): 239–56. http://dx.doi.org/10.7733/jnfcwt.2017.15.3.239.
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Kim, Jun-Mo. „Deep borehole disposal of high-level radioactive waste and spent nuclear fuel“. Journal of the geological society of Korea 51, Nr. 4 (31.08.2015): 425. http://dx.doi.org/10.14770/jgsk.2015.51.4.425.
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Yang, Qing Chun, Wei Lu und Ping Li. „A Numerical Sensitivity Analysis to Bentonite Parameters for a Long Term Geochemical Evolution of a HLW Repository in Clay“. Advanced Materials Research 356-360 (Oktober 2011): 1258–61. http://dx.doi.org/10.4028/www.scientific.net/amr.356-360.1258.
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Deep geological disposal (DGD) is selected for the long-term confinement of high-level radioactive waste (HLW) by many countries. Safety assessment of nuclear waste disposal in a deep geological repository requires understanding and quantifying radionuclide behavior through the hosting geological formation. This paper presents a numerical model to deal with the pore water composition in bentonite barrier in the evolving geochemical environment which includes bentonite, concrete and clay in a high level radioactive waste repository designed in clay formation, the model considers the following processes: advection, diffusion, aqueous complexation, mineral dissolution/precipitation and cation exchange. Bentonite porosity changes caused by mineral dissolution/precipitation reactions are taken into account in the model. The numerical sensitivity analysis to the accessible porosity of bentonite are performed, the results illustrate that the pH in bentonite is sensitive to changes in accessible porosity of bentonite, the concentrations of aqueous species are sensitive to bentonite porosity before 1000 years, and the effective diffusion coefficient of bentonite controls the extent of high pH plume in bentonite.
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Chaudry, Saleem, Angelika Spieth-Achtnich und Wilhelm Bollingerfehr. „Management of high-level radioactive waste in Germany: roads from storage towards disposal – need and options for action“. Safety of Nuclear Waste Disposal 1 (10.11.2021): 217–18. http://dx.doi.org/10.5194/sand-1-217-2021.
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Abstract. The road towards final disposal of high-level radioactive waste (HAW) produced in Germany requires extensive and foresighted management. To date, HAW has been stored in dual-purpose casks inside 15 interim storage facilities. Finally, it is disposed of in a deep geological repository. A site-selection process for this repository, taking into account the whole national territory, started in 2017. The road from interim storage to final disposal is not yet planned in detail: neither temporally nor spatially nor technically. Important parameters are still unknown. The last operating licenses of the existing interim storage facilities, originally built to last for up to 40 years, will end in 2047, and a concept for prolonged interim storage does not exist. The dates for the decision on the repository site and the start of its operation are plagued by uncertainties, as well as the development of safety concepts for different potential host rocks or knowledge on the long-time behavior of disused fuel assemblies during dry interim storage. According to the German site-selection law (Deutscher Bundestag, 2017) the siting decision for the final repository is planned to be made in 2031; Thomauske and Kudla (2016) drew up timelines for the site-selection process to end between 2059 and 2096. The research project WERA – Management of high-level radioactive waste in Germany: Roads from storage towards disposal – addressed these uncertainties through the development of different design options for the four main steps of the German road to disposal and of a variety of scenarios combining these steps, covering a broad range of potential future designs of the road to disposal. These scenarios have been analyzed in detail. Need for technical and political action along the road to final disposal has been identified. Options for action were named, and their preconditions and consequences were listed. The design options and the scenarios derived form the basis of societal discourse on the disposal of high-level radioactive waste. Thus, the research project WERA contributes toward the politically and societally active integration of the different disposal steps (interim storage, receiving storage facility, waste conditioning, and final disposal).