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Relevant bibliographies by topics / Nuclear facilities-Waste disposal

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Academic literature on the topic 'Nuclear facilities-Waste disposal'

Author: Grafiati

Published: 4 June 2021

Last updated: 10 February 2022

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Journal articles on the topic "Nuclear facilities-Waste disposal"

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Ojovan, Michael I., Rebecca A. Robbins, and Miklos Garamszeghy. "Advances in conditioning of low- and intermediate-level nuclear waste." MRS Advances 3, no. 19 (December 10, 2017): 983–90. http://dx.doi.org/10.1557/adv.2017.613.

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ABSTRACTRadioactive waste with widely varying characteristics is generated from the operation and maintenance of nuclear reactors, nuclear fuel cycle facilities, research facilities and medical facilities and the through the use of radioisotopes in industrial applications. The waste needs to be treated and conditioned appropriately to provide wasteforms acceptable for safe storage and disposal. Conditioning of radioactive waste is an important step to prepare waste for long-term storage or disposal and includes the following processes:▪ Immobilization which may or may not also provide volume reduction, includinga) Low temperature processes andb) Thermal processes;▪ Containerization fora) Transport,b) Storage, andc) Disposal;▪ Overpacking of primary containersa) Prior to disposal andb) In a disposal facility as part of disposal process.Conditioning consists of operations that produce a waste package suitable for handling, transportation, storage and/or disposal and may be performed for a variety of reasons including standardization of practices and/or wasteforms, technical requirements for waste stability in relation to a repository design or safety case, technical requirements related to waste transportation, societal preferences, regulatory preferences, etc. This paper gives an overview of recent advances in conditioning of low- and intermediate-level radioactive waste.The paper is based on the new IAEA Handbook “Conditioning of Low- and Intermediate-Level Liquid, Solidified and Solid Waste” which is one of eight IAEA handbooks intended to provide guidance for evaluating and implementing various characterisation and radioactive waste processing and storage technologies before final disposal

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Vnukov, V. S., B. G. Ryazanov, and V. I. Sviridov. "Nuclear Safety of Disposal Facilities for Radioactive Waste Containing Fissile Nuclear Materials." Radioactive waste, no. 3 (2019): 44–52. http://dx.doi.org/10.25283/2587-9707-2019-3-44-52.

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Ojovan, Michael I., and Zoran Drace. "Processing and Disposal of Radioactive Waste: Selection of Technical Solutions." MRS Proceedings 1518 (2012): 203–9. http://dx.doi.org/10.1557/opl.2012.1569.

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ABSTRACTAn overview of selection criteria for waste processing and disposal technologies is given. A systematic approach for selection of an optimal technology is proposed. Optimal selection of a technical processing and disposal option is case specific to the waste management needs. Waste streams considered are from nuclear applications, research, power generation, nuclear fuel cycle activities and decommissioning of nuclear facilities as well as for NORM-containing waste.

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Muller, Richard A., Stefan Finsterle, John Grimsich, Rod Baltzer, Elizabeth A. Muller, James W. Rector, Joe Payer, and John Apps. "Disposal of High-Level Nuclear Waste in Deep Horizontal Drillholes." Energies 12, no. 11 (May 29, 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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Devgun, J. S. "Suitability of unconsolidated sediments for hosting low-level radioactive waste disposal facilities." Canadian Journal of Civil Engineering 16, no. 4 (August 1, 1989): 560–67. http://dx.doi.org/10.1139/l89-086.

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Among the unconsolidated sediments, sand deposits are considered a rather unconventional geologic host medium for siting radioactive waste repositories, the clays being the preferred choice. A closer examination of the various geologic media, however, shows that in each case there are advantages and disadvantages. The key to safe and cost-effective disposal is to match the engineered design of the facility to the site's characteristics as well as the nature of the waste to be disposed of. In humid climates, free-draining sediments such as sand can provide the advantage of eliminating concern related to the “bathtub effect.”At Chalk River Nuclear Laboratories (CRNL), a sand dune has been proposed for hosting a low-level radioactive waste disposal facility. This paper discusses the suitability of unconsolidated sediments for radioactive waste disposal in general; in particular, it provides the rationalization for the selection of a sand dune as the host site at CRNL. Key words: radioactive waste, disposal facilities, unconsolidated sediments, site suitability, trench cover materials, sreismicity, soil liquefaction.

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Bugai, D., and R. Avila. "Scenarios and Pathways of Radionuclide Releases from Near-Surface Waste Disposal Facilities: A Brief Overview of Historical Evidence." Nuclear and Radiation Safety, no. 3(87) (September 15, 2020): 21–27. http://dx.doi.org/10.32918/nrs.2020.3(87).03.

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The very low-level waste (VLLW) produced during decommissioning of nuclear facilities can be suitable for disposal in landfill type facilities. Considering the similarities in design, the experience gained in near-surface disposal of radioactive waste in trenches and vaults is relevant to the issue of VLLW disposal in landfills. This paper presents a brief review of internationally reported cases of radionuclide releases from near-surface disposal facilities. Based on this review, the conclusions are made that the following radionuclide release and exposure scenarios should be accounted for in safety assessment of VLLW disposal in landfills: i) leaching from waste to groundwater by atmospheric precipitations; ii) bath-tubing scenario; iii) scenarios caused by extreme meteorological and hydrological events (erosion, flooding, etc.); iv) human intrusion. The gaseous transport deserves attention for a number of relevant radionuclides, such as (C-14, Rn-222, etc.). In addition, the possibility of early degradation of engineered containment structures (soil covers, bottom seals) should be cautiously considered.

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Johnson, L. H., and L. O. Werme. "Materials Characteristics and Dissolution Behavior of Spent Nuclear Fuel." MRS Bulletin 19, no. 12 (December 1994): 24–27. http://dx.doi.org/10.1557/s088376940004865x.

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The geologic disposal of spent nuclear fuel is currently under consideration in many countries. Most of this fuel is in the form of assemblies of zirconium-alloy-clad rods containing enriched (1–4% 235U) or natural (0.71% 235U) uranium oxide pellets. Approximately 135,000 Mg are presently in temporary storage facilities throughout the world in nations with commercial nuclear power stations.Safe geologic disposal of nuclear waste could be achieved using a combination of a natural barrier (the host rock of the repository) and engineered barriers, which would include a low-solubility waste form, long-lived containers, and clay- and cement-based barriers surrounding the waste containers and sealing the excavations.A requirement in evaluating the safety of disposal of nuclear waste is a knowledge of the kinetics and mechanism of dissolution of the waste form in groundwater and the solubility of the waste form constituents. In the case of spent nuclear fuel, this means developing an understanding of fuel microstructure, its impact on release of contained fission products, and the dissolution behavior of spent fuel and of UO2, the principal constituent of the fuel.

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Churakov, Sergey V., Wolfgang Hummel, and Maria Marques Fernandes. "Fundamental Research on Radiochemistry of Geological Nuclear Waste Disposal." CHIMIA International Journal for Chemistry 74, no. 12 (December 23, 2020): 1000–1009. http://dx.doi.org/10.2533/chimia.2020.1000.

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Currently, 5 · 1019 Bq of radioactive waste originating from the use of nuclear power for energy production, and medicine, industry and research, is maintained in Switzerland at intermediate storage facilities. Deep geological disposal of nuclear waste is considered as the most reliable and sustainable long-term solution worldwide. Alike the other European countries, the Swiss waste disposal concept embarks on the combination of engineered and geological barriers. The disposal cell is a complex geochemical system. The radionuclide mobility and consequently radiological impact depend not only on their chemical speciation but also on the background concentration of other stable nuclides and their behaviour in the natural environment. The safety assessment of the repository is thus a complex multidisciplinary problem requiring knowledge in chemical thermodynamics, structural chemistry, fluid dynamics, geo- and radiochemistry. Broad aspects of radionuclide thermodynamics and geochemistry are investigated in state-of-the-art radiochemical laboratories at the Paul Scherrer Institute. The research conducted over the last 30 years has resulted in a fundamental understanding of the radionuclides release, retention and transport mechanism in the repository system.

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Chen, Hai Ying, Chun Ming Zhang, Shao Wei Wang, Qiao Feng Liu, and Jing Ru Han. "Discussion on Very Low-Level Radioactive Waste near Surface Disposal." Advanced Materials Research 807-809 (September 2013): 1207–10. http://dx.doi.org/10.4028/www.scientific.net/amr.807-809.1207.

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Radioactive waste disposal is one of the most sensitive environmental problems. As the arriving of decommissioning of early period nuclear facilities in China, large amounts of very low-level radioactive waste will be produced inevitably. The domestic and abroad definitions about very low-level radioactive waste and its disposal were introduced, and then siting principles of near surface disposal of very low-level radioactive waste were discussed. The near surface disposal sites’ natural barriers were analyzed from the crustal structure and the radionuclide adsorption characteristics of natural barriers. The near surface disposal sites’ engineering barriers were analyzed from the repository design and the repository barrier materials selection. Finally, the improving direction of very low-level radioactive waste disposal was proposed, which would promote the study of very low-level radioactive waste disposal in China.

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Watanabe, Yasutaka, and Shingo Yokoyama. "Research on a long-term behavior of radioactive waste disposal facilities." Journal of the Atomic Energy Society of Japan 59, no. 3 (2017): 142–46. http://dx.doi.org/10.3327/jaesjb.59.3_142.

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Dissertations / Theses on the topic "Nuclear facilities-Waste disposal"

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

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Saurí, Suárez Héctor [Verfasser], and R. [Akademischer Betreuer] Stieglitz. "Individual dosimetry in disposal facilities for high-level nuclear waste / Héctor Saurí Suárez ; Betreuer: R. Stieglitz." Karlsruhe : KIT-Bibliothek, 2018. http://d-nb.info/1162540648/34.

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Books on the topic "Nuclear facilities-Waste disposal"

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Krochmalnek, L. S. Conditioning and handling of tritiated wastes at Canadian nuclear power facilities. Mississauga, Ont: CFFTP, 1987.

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Frankena, Frederick. Radioactive waste problems at commercial nuclear facilities and disposal sites: A bibliography. Monticello, Ill., USA: Vance Bibliographies, 1991.

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Corrosion, European Federation of. A working party report on corrosion problems related to nuclear waste disposal. London: The Institute of Materials, 1992.

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Nuclear Waste Issues Conference (1986 University of Winnipeg). Challenges to nuclear waste: Proceedings of the Nuclear Waste Issues Conference, September 12-14, 1986. [Winnipeg]: The Conference, 1987.

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5

Fuchs, Ronald L. 1992 state-by-state assessment of low-level radioactive wastes received at commercial disposal sites. Idaho Falls, Idaho: National Low-Level Waste Management Program, 1993.

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Donders, R. E. Managing LLRW from decommissioning of nuclear facilities: A Canadian perspective. Chalk River, Ont: Chalk River Laboratories, 1994.

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International Conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities (2006 Athens, Greece). Lessons learned from the decommissioning of nuclear facilities and the safe termination of nuclear activities: Proceedings of an International Conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities. Vienna: International Atomic Energy Agency, 2007.

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International Symposium on Experience in the Planning and Operation of Low Level Waste Disposal Facilities (1996 Vienna, Austria). Planning and operation of low level waste disposal facilities: Proceedings of an International Symposium on Experience in the Planning and Operation of Low Level Waste Disposal Facilities. Vienna: The Agency, 1996.

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William, Hevly Bruce, ed. Atomic frontier days: Hanford and the American West. Seattle: Center for the Study of the Pacific Northwest in association with University of Washington Press, 2011.

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United States. Dept. of Energy. Idaho Operations Office. Idaho high-level waste & facilities disposition. [Idaho Falls, ID: The Office, 1999.

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Book chapters on the topic "Nuclear facilities-Waste disposal"

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Di Nucci, Maria Rosaria. "Voluntarism in Siting Nuclear Waste Disposal Facilities." In Energiepolitik und Klimaschutz. Energy Policy and Climate Protection, 147–74. Wiesbaden: Springer Fachmedien Wiesbaden, 2019. http://dx.doi.org/10.1007/978-3-658-27107-7_9.

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Mašín, David. "Modelling of Bentonite for Nuclear Waste Disposal Facilities with Hypoplasticity." In Desiderata Geotechnica, 93–98. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-14987-1_11.

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Nataraj, Mysore S. "Preliminary Geotechnical Evaluation of Deep Borehole Facilities for Nuclear Waste Disposal in Shales." In Frontiers in Sedimentary Geology, 539–43. New York, NY: Springer New York, 1991. http://dx.doi.org/10.1007/978-1-4612-4428-8_57.

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Bederdinov, V. A., V. K. Bulygin, Yu A. Sderzhikov, V. A. Vassilenko, V. N. Epimakhov, A. A. Efimov, V. G. Iliyn, V. V. Kobekov, and V. A. Melnikov. "Development of Safe Technologies for Handling Liquid Radioactive Waste at Naval Sites/Facilities: Experience and Prospects." In Analysis of Risks Associated with Nuclear Submarine Decommissioning, Dismantling and Disposal, 419–24. Dordrecht: Springer Netherlands, 1999. http://dx.doi.org/10.1007/978-94-011-4595-4_49.

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Malyshev, S. P. "Small Mobile Installation for Reprocessing of Radioactive Waste from Technological Circuits of Nuclear Power Facilities of Nuclear Submarines Subject to Recycling." In Analysis of Risks Associated with Nuclear Submarine Decommissioning, Dismantling and Disposal, 405–18. Dordrecht: Springer Netherlands, 1999. http://dx.doi.org/10.1007/978-94-011-4595-4_48.

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Kuno, Michiya, and Masanori Hamada. "Radioactive Waste Treatment and Disposal Technique." In Earthquake Engineering for Nuclear Facilities, 211–28. Singapore: Springer Singapore, 2016. http://dx.doi.org/10.1007/978-981-10-2516-7_11.

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"Institutional Aspects of Siting Nuclear Waste Disposal Facilities in the United States *." In Nuclear Power in Crisis, edited by John Cameron Stewart and W. Clark Prichard, 164–77. Routledge, 2019. http://dx.doi.org/10.4324/9780429278242-7.

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Kuippers, Gina, Naji M. Bassil, and Jonathan R. Lloyd. "Microbial colonization of cementitious geodisposal facilities, and potential “biobarrier” formation." In The Microbiology of Nuclear Waste Disposal, 157–92. Elsevier, 2021. http://dx.doi.org/10.1016/b978-0-12-818695-4.00008-3.

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Blechschmidt, I., and S. Vomvoris. "Underground research facilities and rock laboratories for the development of geological disposal concepts and repository systems." In Geological Repository Systems for Safe Disposal of Spent Nuclear Fuels and Radioactive Waste, 82–118. Elsevier, 2010. http://dx.doi.org/10.1533/9781845699789.1.82.

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Conference papers on the topic "Nuclear facilities-Waste disposal"

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Mahar, James M., Jay F. Kunze, and Carl W. Myers. "Underground Nuclear Power Parks: Power Plant Design Implications." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48889.

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The siting of nuclear power plants underground, along with associated reprocessing, fuel manufacturing, and high level waste disposal facilities offer many advantages. Security costs are substantially less, radiative package transportation issues are eliminated, and political issues of high level waste storage and disposal are largely eliminated. Keeping the site preparation costs to a minimum requires that the underground facilities accommodate several power producing units (nominally 6 GW or more). However, significant redesign and placement of components can make it possible to accomplish most of the underground excavation with tunnel boring machines. These latter issues are addressed in this paper.

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Weihong, Yue, and Xu Yeqiang. "In Situ Measurement Technique of Low-Energy β-Contaminated Waste Sorting." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81341.

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Operation and decommissioning of nuclear facilities will produce radioactive waste, and different radionuclides in the waste will bring different hazards to the public and the environment. The waste would be sorted more reasonably by distinguishing different radionuclides. Yet it is still very difficult to measure directly the pure Beta radioactive waste in situ, though in situ Gamma-analytical and Alpha-waste-barrel measurement techniques have become more sophisticated. The aim is to propose a scientific technique to sort the radioactive waste in situ. This study focused on the 90Sr-contaminated material in China Institute of Atomic Energy and optimized the design of the existing solid waste disposal facilities. A novel technique to measure the radioactive waste 90Sr-90Y online was proposed, trying to sort the radioactive waste as optimally as possible to realize further separation of exemption waste. Theoretically, the exemption waste can be further sorted, and it can guide the design of radioactive waste disposal system.

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de Lemos, Francisco Luiz, Karl-Heinz Helmuth, and Terry Sullivan. "Transparent Tools for Uncertainty Analysis in High Level Waste Disposal Facilities Safety." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7277.

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In this paper some results of a further development of a technical cooperation project, initiated in 2004, between the CDTN/CNEN, The Brazilian National Nuclear Energy Commission, and the STUK, The Finnish Radiation and Nuclear Safety Authority, are presented. The objective of this project is to study applications of fuzzy logic, and artificial intelligence methods, on uncertainty analysis of high level waste disposal facilities safety assessment. Uncertainty analysis is an essential part of the study of the complex interactions of the features, events and processes, which will affect the performance of the HLW disposal system over the thousands of years in the future. Very often the development of conceptual and computational models requires simplifications and selection of over conservative parameters that can lead to unrealistic results. These results can mask the existing uncertainties which, consequently, can be an obstacle to a better understanding of the natural processes. A correct evaluation of uncertainties and their rule on data interpretation is an important step for the improvement of the confidence in the calculations and public acceptance. This study focuses on dissolution (source), solubility and sorption (sink) as key processes for determination of release and migration of radionuclides. These factors are affected by a number of parameters that characterize the near and far fields such as pH; temperature; redox conditions; and other groundwater properties. On the other hand, these parameters are also consequence of other processes and conditions such as water rock interaction; pH and redox buffering. Fuzzy logic tools have been proved to be suited for dealing with interpretation of complex, and some times conflicting, data. For example, although some parameters, such as pH and carbonate, are treated as independent, they have influence in each other and on the solubility. It is used the technique of fuzzy cognitive mapping is used for analysis of effects of variations on one parameter on the others in a system. This technique uses the concept of fuzzy sets to represent the “quality” of the relation between parameters rather then deterministic numbers.

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Gupalo, T. A., V. V. Lopatin, and N. F. Lobanov. "Current Status of Radioactive Waste Disposal in Russia." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4532.

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A huge amount of radioactive waste has been accumulated in the Russian Federation (RF) in the course of implementation of the defense and energy programs, industrial and research activity involving the use of nuclear materials. The most justified and technically feasible technology of solidified RW isolation is its disposition in low-permeable geological formations in specially constructed underground facilities. Today in Russia a Closed Fuel Cycle (CFC) has been adopted, at the CFC final stage the spent nuclear materials and radioactive waste have to be isolated from the biosphere for the whole term of their potential hazard. In Russia, in accordance with the regional approach to the decision of Radioactive Waste (RW) disposal problem, several candidate disposal sites have been assigned.

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Dutzer, Michel, Ge´rald Ouzounian, Roberto Miguez, and Jean-Louis Tison. "Radioactive Waste: Feedback of 40-Year Operations in France." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40081.

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France’s experience in the management of radioactive waste is supported by forty years of operational activities in the field of surface disposal. This feedback is related to three disposal facilities: Centre de la Manche disposal, not far away Cherbourg, from design to post-closure facility. Centre at Soulaines-Dhuys from site selection to design to operation during nearly 20 years. Centre at Morvilliers from site selection to operation for seven years now. During the operational period of Centre de la Manche disposal facility (1969–1994), the safety concept for low- and intermediate level short lived waste (LIL-SLW) was developed and progressively incorporated in the procedures of the facility. The facility entered its institutional control period and the experience of this facility has been useful for the operating facilities. Centre de l’Aube that took over Centre de la Manche, and Morvilliers for very low level wastes. Both facilities currently accommodate the major part of the volume of radioactive wastes that are generated in France. However disposal facilities have to be considered as rare resources. Then new waste management options are being investigated as the disposal of large components or recycling metallic wastes within the nuclear industry.

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Needham, Michael. "Detecting Sources of Ionizing Radiation in the Waste Stream." In 10th Annual North American Waste-to-Energy Conference. ASMEDC, 2002. http://dx.doi.org/10.1115/nawtec10-1016.

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Why is the detection of radioactive sources important to the solid waste industry?: Radioactive material is used extensively in the United States in research, medicine, education, and industry for the benefit of society (e.g. smoke detectors, industrial process gauges, medical diagnosis/treatment). Generally speaking, the Nuclear Regulatory Commission and state governments regulate the use and disposal of radioactive materials. Licensed radioactive waste disposal facilities receive the bulk of the waste generated in the United States with exceptions for low-level waste (e.g. medical patient waste) that may be disposed of as municipal waste. According to the Conference of Radiation Control Program Directors, Inc (CRCPD)., there has been an increasing number of incidence involving the detection of prohibited radioactive wastes at solid waste management facilities. While the CRCPD acknowledges that the increased incidence may be partially attributed to the growing number of solid waste facilities that have detection systems, undetected sources of ionizing radiation can harm the environment, have a negative impact on employee health and safety, and result in significant remedial actions. Implementing an effective detection/response plan can aid in the proper management of radioactive waste and serve to minimize the potential for negative outcomes.

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Yakimenco, T. V., T. I. Paramonova, and V. A. Smirnov. "Doses Forming Paths of External Irradiation of Personnel on Radioactive Waste Disposal Facilities." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4873.

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The centralized system of radioactive waste management formed beyond of a nuclear fuel cycle exist in Russia. In territory of Russian Federation 16 regional specialized combines (SO) “Radon” are located, the majority of them is entered into operation in the first half 60th years. The specialized combines “Radon” are carrying out centralized collection, RW transportation, processing, localization and long-term storage of RW low and average activity, delivery service of new sources of ionizing radiation to users, take part in liquidation of radioactive contamination of served territory, carry out an nature-conservative measures of pollution prevention of the environment fromradioactive substances and ensuring radiation safety of population. For years of their existence total number of the personnel has made hundreds person. In most cases the personnel of combines are under a radiation control since time of introduction of objects in operation, about 40 years.

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McCombie, Charles. "New Nuclear Programmes Must Not Neglect Waste Management." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59077.

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Many established nuclear power programmes have learned to their dismay that waste management and disposal are not tasks that can be postponed at will if public and political acceptance is a prerequisite for progress. In fact, some programmes that recognised this back in the 1970s and 1980s moved into leading positions in repository development. This happened, for example, in Sweden and Switzerland where already in the 1970s Laws were passed specifying that safe disposal must be demonstarted before new nuclear plants could opersate. In recent years, it has become recognised that, in order to ensure that the radioactive wastes in any country are managed safely, it is necessary to have an established legislative and regulatory framework and also to create the necessary organizations for implementation and for oversight of waste management operations and facility development. Guidance on these issues is given in the Joint Convention and a number of other IAEA documents. The IAEA, and also the EC, have in addition published key overarching advisory documents for new nuclear programmes. These are useful for strategic planning but, when it comes to actual implementation projects, the advice tends to imply that all nuclear programmes, however large or small, should be pressing ahead urgently towards early operation of geological repositories. In practice, however, in small programmes there are neither economic nor technical drivers for early implementation of deep geological repositories. Constructing simpler facilities for the disposal of the larger volume of low-level wstes has higher priority. Nevertheless, in all countries political decisions have to be taken and policies set in place to ensure that geological disposal will implemented without unjustified delay. This paper distils out a set of key messages for new programmes. Amongst the most critical are the following. Even if disposal is far off, planning and organization should begin at the initiation of the programme; this can help with technical and economic optimization and (importantly) also with public and political acceptance. Important lessons can be learned from advanced programmes — but these must be adapted to allow for the different boundary conditions of new and small programmes. The key differences relate to the timescales involved, and the resources available. There is a range of waste management and waste disposal options open to new programmes. It is not necessary to choose definitive solutions at the outset; options can be kept open, but a minimum level of engagement is required for all open options.

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Cantarella, J., R. Simenon, and M. Braeckeveldt. "Activities ONDRAF/NIRAS Related to the Decommissioning of Nuclear Facilities." In ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96174.

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Since 1980, the Agency is responsible by law for the safe management of all radioactive waste produced in Belgium, including decommissioning wastes. By the law of 11 January 1991 and the implementing Royal Decree of 16/10/1991, ONDRAF/NIRAS has been entrusted with a mission concerning the decommissioning of nuclear facilities. This mission involves the collection and assessment of data concerning decommissioning forecasts for nuclear facilities, the approval of facilities’ decommissioning programmes, the establishment — in consultation with operators — of financing conditions for decommissioning, as well as the implementation of these programmes on request by the operator, or in the case of its failure to do so. This is the case for the company Best Medical Belgium SA located at Fleurus (MDS Nordion SA, till April 2011), which produced radioisotopes for medical applications and went bankrupt in 2012. These installations have been entrusted to ONDRAF/NIRAS. A plan of action was developed for taking-over the operations in the framework of remediation and decommissioning. Steps have been taken to integrate his new role as a nuclear operator. The installations of Best Medical Belgium SA are now referred to as the “O/N - Site Fleurus.” Nuclear facility operators, or any person requesting to operate a nuclear facility, are obliged to provide ONDRAF/NIRAS, under their responsibility and in due time, with all the necessary information concerning these facilities’ decommissioning forecasts, the nature, quantities and dates of transfer of the resulting waste, and the financing conditions for these facilities’ decommissioning. In order to make the necessary funds available for decommissioning a nuclear facility when it will be shut down, operators are obliged to establish provisions during the facility’s active life. These provisions are calculated in such a way that the total amount established at the time of the final shutdown covers all costs resulting from the facility’s final phase, namely the preparation of decommissioning, decontamination, more or less long-term maintenance, dismantling, treatment, conditioning and disposal of waste produced during this phase. In order to face to multiple and repeated evaluation processes, the Agency, already in the early 90’s, started with the implementation of its own integrated data processing system, recording the physical and radiological inventories of nuclear facilities, and allowing the evaluation of the quantities of decommissioning materials and wastes as well as of the decommissioning costs of these facilities. The cost evaluations cover all decommissioning activities from final shutdown of the facility until final release from nuclear control, as well as conventional demolition and site restoration if required. Beside the information related to the inventories, the database involves so called auxiliary tables integrating unit prices of the various decontamination and dismantling techniques, unit rates for radioactive waste processing, interim storage and final disposal.

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Delay, Jacques, Jiri Slovak, and Raymond Kowe. "The Implementing Geological Disposal Technology Platform: Key Challenges in Research and Development in Radioactive Waste Management." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30962.

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The Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP) was launched in November 2009 to tackle the remaining research, development and demonstration (RD&D) challenges with a view to fostering the implementation of geological disposal programmes for high-level and long-lived waste in Europe. The IGD-TP’s Vision is that “by 2025, the first geological disposal facilities for spent fuel, high-level waste and other long-lived radioactive waste will be operating safely in Europe”. Aside from most of European waste management organisations, the IGD-TP now has 110 members covering most of the RD&D actors in the field of implementing geological disposal of radioactive waste in Europe. The IGD-TP Strategic Research Agenda (SRA), that defines shared RD&D priorities with an important cooperative added value, is used as a basis for the Euratom programme. It provides a vehicle to emphasise RD&D and networking activities that are important for establishing safety cases and fostering disposal implementation. As the IGD-TP brings together the national organisations which have a mandate to implement geological disposal and act as science providers, its SRA also ensures a balance between fundamental science, implementation-driven RD&D and technological demonstration. The SRA is in turn supported by a Deployment Plan (DP) for the Joint Activities to be carried out by the Technology Platform with its members and participants. The Joint Activities were derived from the individual SRA Topics and prioritized and assigned a timeline for their implementation. The deployment scheme of the activities is updated on a yearly basis.

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Reports on the topic "Nuclear facilities-Waste disposal"

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Moore, Robert Charles, Ahmed Ali Mohamed Hasan, Kathleen Caroline Holt, and Mahmoud A. Hasan. Overview on backfill materials and permeable reactive barriers for nuclear waste disposal facilities. Office of Scientific and Technical Information (OSTI), October 2003. http://dx.doi.org/10.2172/917140.

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2

Nataraj, M. S. Preliminary geotechnical evaluation of deep borehole facilities for nuclear waste disposal in shales. Office of Scientific and Technical Information (OSTI), January 1991. http://dx.doi.org/10.2172/6149174.

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