Academic literature on the topic 'Final storage of radioactive waste'

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Journal articles on the topic "Final storage of radioactive waste"

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Glasser, F. P., and M. Atkins. "Cements in Radioactive Waste Disposal." MRS Bulletin 19, no. 12 (1994): 33–38. http://dx.doi.org/10.1557/s0883769400048673.

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Depending on their radioactive content and abundance of long-lived radionuclides, radioactive wastes are often described as low, intermediate or high-level. Cements play a major role in the engineered structures, existing and planned, of most national programs for low- and intermediate-level (ILW) radioactive wastes. Final disposal of ILW is usually by burial at considerable depth (>250 meters), e.g., in planned repositories in clay at Mol (Belgium), in salt at Gorleben (Germany), and in volcanic tuffs at Sellafield (United Kingdom). A sample disposal concept is shown in Figure 1. Shallow l
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Neubauer, Josef. "Radioactive waste management in Austria." Nuclear Technology and Radiation Protection 19, no. 2 (2004): 59–64. http://dx.doi.org/10.2298/ntrp0402059n.

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At the Austrian Research Centers Seibersdorf, there are several facilities in stalled for treatment of waste of low and intermediate radioactivity level (radwaste). A separate company within Centers, Nuclear Engineering Seibersdorf, has been formed recently, acting as a centralized facility for treatment, conditioning and storing of such waste within the country. The relevant treatment technology is applied depending on the waste category. In total about 6900 m3 of solid waste of low and intermediate radioactivity level originating from Austria was treated in the period between 1976 and 2002.
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Iarmosh, I., S. Kondratiev, L. Kuechler, O. Tokarevskyi, and O. Solovyov. "Approaches to characterization of radioactive waste in Ukraine at interrelated steps of their management." Nuclear and Radiation Safety, no. 1(85) (March 13, 2020): 41–49. http://dx.doi.org/10.32918/nrs.2020.1(85).04.

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A key point for safety assessments at different steps of radioactive waste (RW) management is the knowledge of all the relevant properties of materials that are to be disposed of as RW or cleared from regulatory control (immediately or after a certain period of time for decay storage). Characterization is the basis for the determination of radiological and non-radiological hazards of the radioactive materials and waste.
 This paper considers approaches for a systemized characterization of radioactive waste at all steps of its management from generation to disposal. These approaches ensure
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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 (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 r
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Rosnovsky, Sergey V., and Vladimir P. Povarov. "Ensuring radiation safety during temporary storage of solidified radioactive waste in light hangar-type facilities." Nuclear Energy and Technology 7, no. 3 (2021): 195–99. http://dx.doi.org/10.3897/nucet.7.73487.

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Expensive permanent storage facilities with massive engineered structures are used traditionally to ensure safe temporary storage of solidified radioactive waste at the NPP sites. Such approach is dictated by the need to comply with the regulatory requirements for limiting the gamma background in the area adjacent to the storage facility. The costs involved in temporary storage of solidified RW can be optimized by using light hangar-type storage facilities. At the same time, the safety of storage, including radiation protection of the personnel, the public and the environment, is undoubtedly e
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Stefanovsky, Sergey V., Yuri V. Myshkin, Dmitri V. Adamovich, and Michael D. Beliy. "RADON Operational Experience in High-Temperature Treatment of Radioactive Wastes." Advances in Science and Technology 94 (October 2014): 121–30. http://dx.doi.org/10.4028/www.scientific.net/ast.94.121.

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FSUE Radon deals with collection, transportation, treatment, conditioning, and interim storage and final disposal of conditioned low-and intermediate-level radioactive wastes (LILW) as well as radiation monitoring, decontamination and environmental remediation of Moscow and Moscow area. Liquid LILW with high salinity is subject to vitrification at the Radon full scale vitrification plant using a cold crucible inductive melting (CCIM) at temperatures of 1150-1200 °C. The bench-scale cold crucible based unit is used for research works and feasibility study on new promising ceramic and glass-cera
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Sanders, Charlotta E. "Review of the Development of the Proposed Yucca Mountain Geologic Repository." Advances in Science and Technology 94 (October 2014): 115–20. http://dx.doi.org/10.4028/www.scientific.net/ast.94.115.

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It can be said that the nuclear community neglected the issue of final storage of nuclear waste in the first era of nuclear power production, with many nations not looking at this topic until some years into its program. This is a matter that must not be neglected now during the ‘renaissance’ of nuclear if nuclear energy is to have a part on the stage of the play in world energy supplies. In 1982, the United States (U.S.) Congress passed the Nuclear Waste Policy Act (NWPA), which outlines the screening process for selecting a national site for used nuclear fuel and high-level radioactive waste
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Tantau, Adrian, and Greta-Marilena Vitioanu. "Key factors affecting disposal of radioactive waste in the sustainable development approach." Proceedings of the International Conference on Business Excellence 14, no. 1 (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
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Balderer, Werner. "The NAGRA investigation project for the assessment of repositories for high-level radioactive waste in geological formations." Mineralogical Magazine 49, no. 351 (1985): 281–88. http://dx.doi.org/10.1180/minmag.1985.049.351.15.

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AbstractThe first results of isotopic investigations as a part of the hydrogeological study of northern Switzerland are presented. This study is part of the global geological research project of the NAGRA (National Co-operative for the Storage of Radioactive Waste) which is intended to provide the scientific knowledge required for the assessment of the feasibility of safe disposal of highly radioactive waste in the geological formations of the area. The aim of the hydrogeological research programme is to assess the natural conditions in the sedimentary sequence and the underlying granite basem
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Hyatt and Ojovan. "Special Issue: Materials for Nuclear Waste Immobilization." Materials 12, no. 21 (2019): 3611. http://dx.doi.org/10.3390/ma12213611.

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Nuclear energy is clean, reliable, and competitive with many useful applications, among which power generation is the most important as it can gradually replace fossil fuels and avoid massive pollution of environment. A by-product resulting from utilization of nuclear energy in both power generation and other applications, such as in medicine, industry, agriculture, and research, is nuclear waste. Safe and effective management of nuclear waste is crucial to ensure sustainable utilization of nuclear energy. Nuclear waste must be processed to make it safe for storage, transportation, and final d
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Dissertations / Theses on the topic "Final storage of radioactive waste"

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LEITE, ELIANA R. "Indicadores de segurança para um d´pósito final de fontes radioativas seladas." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10142.

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Made available in DSpace on 2014-10-09T12:35:13Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T13:57:01Z (GMT). No. of bitstreams: 0<br>Dissertação (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Franzén, Jonas, and Jim Kautto. "Kampanjmottagande : Hur tas Regionförbundet i Kalmar läns kampanj om slutförvar av använt kränbränsle emot av målgruppen?" Thesis, University of Kalmar, School of Communication and Design, 2009. http://urn.kb.se/resolve?urn=urn:nbn:se:hik:diva-1928.

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<p>Authors: Jonas Franzén and Jim Kautto</p><p>Title: Information campaign analysis of the Region Council of Kalmar Counties public information campaign about final storage of radioactive waste.</p><p>Level: BA Thesis in Media and Communication Studies.</p><p>Key words: Campaign, Campaign analysis, final storage of radioactive waste, Region Council.</p><p>Language: Swedish</p><p>Content: The Regional Council of Kalmar County launched a campaign about final storage of radioactive waste in the spring of 2009. This study analyzes how that campaign was received by the target group.</p><p>Theory: F
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Silva, Fábio. "Sistema de gestão integrada de dados para repositórios de rejeitos radioativos (SGI3R)." CNEN - Centro de Desenvolvimento da Tecnologia Nuclear, Belo Horizonte, 2010. http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=134.

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Nenhuma<br>A implantação de um repositório para rejeitos radioativos é um projeto multidisciplinar que demanda além de especialistas de diferentes áreas do conhecimento, a interação com instituições públicas e privadas, dados e informações relacionadas com rejeitos radioativos, geologia, tecnologia etc. Todas as atividades devem estar em conformidade com as normas, requisitos e procedimentos, incluindo a legislação nacional e internacional. A manutenção dos registros de inventário dos rejeitos é um requisito importante regulamentar e deverá estar disponível até mesmo após o encerramento do rep
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Pascual, Christopher C. "Evaporation measurements from simulated nuclear waste storage tanks." Diss., Georgia Institute of Technology, 1996. http://hdl.handle.net/1853/18208.

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Fairlie, Ian. "Radioactive waste : international examination of storage and reprocessing of spent fuel." Thesis, Imperial College London, 1997. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.268029.

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Podruzhina, Tatiana. "Graphite as radioactive waste: corrosion behaviour under final repository conditions and thermal treatment." [S.l.] : [s.n.], 2004. http://deposit.ddb.de/cgi-bin/dokserv?idn=975257641.

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Stoffle, Richard W., Michael J. Traugott, John V. Stone, et al. "Social Assessment of Siting a Low-Level Radioactive Waste Storage Facility in Michigan." School of Natural Resources and Institute for Social Research, The University of Michigan, 1990. http://hdl.handle.net/10150/298951.

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This report presents findings from a social assessment of siting a low­ level radioactive waste storage facility in Michigan. The research focused specifically on how people perceive themselves to be affected by the proposed facility and the degree of community support for and opposition to the facility. Social assessment research in the LLRW project consisted of a telephone survey of Michigan residents and an in-depth ethnographic survey of residents in the tri-state area of Michigan, Indiana and Ohio. Findings from these studies can aid in the development and implementatio
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MIYAKE, ELOISA T. "Determinacao da permeabilidade a gas em conceito usado em repositorios para rejeitos radioativos." reponame:Repositório Institucional do IPEN, 1994. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10392.

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Made available in DSpace on 2014-10-09T12:38:10Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:04:50Z (GMT). No. of bitstreams: 1 05651.pdf: 5599024 bytes, checksum: 2673b4e5195ce313cc827fb7eadc9a2c (MD5)<br>Dissertacao (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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FERREIRA, ROBSON de J. "Desenvolvimento de metodologia para a caracterizacao de fontes radioativas seladas." reponame:Repositório Institucional do IPEN, 2010. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9570.

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Made available in DSpace on 2014-10-09T12:28:09Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:01:44Z (GMT). No. of bitstreams: 0<br>Dissertacao (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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MOURA, LUIZ A. A. de. "Proposta de implantação de um sistema de gestão ambiental no Laboratório de Rejeitos Radioativos do IPEN-SP." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11508.

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Made available in DSpace on 2014-10-09T12:52:40Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:03:10Z (GMT). No. of bitstreams: 0<br>Dissertação (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP
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Books on the topic "Final storage of radioactive waste"

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Cobble, Carl. Transportation impacts on the Tennessee highway system proposed monitored retrievable storage: Final report. Tennessee Dept. of Transportation, 1985.

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U.S. Dept. of Energy. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. U.S. Department of Energy, Office of Environmental Management, 1997.

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Disposition, United States Dept of Energy Office of Fissile Materials. Storage and disposition of weapons-usable fissile materials final programmatic environmental impact statement. U.S. Dept. of Energy, 1996.

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United States. Dept. of Energy. Office of Fissile Materials Disposition. Surplus plutonium disposition final environmental impact statement. U.S. Dept. of Energy, 1999.

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Frost, R. H. Effects of manufacturing variables on performance of high-level waste low carbon steel containers: Final report. Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

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Pusch, Roland. Geological Storage of Highly Radioactive Waste. Springer Berlin Heidelberg, 2008. http://dx.doi.org/10.1007/978-3-540-77333-7.

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Additional information on monitored retrievable storage. U.S. Dept. of Energy, Office of Civilian Radioactive Waste Management, 1987.

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Management, United States Dept of Energy Office of Civilian Radioactive Waste. Additional information on monitored retrievable storage. U.S. Dept. of Energy, Office of Civilian Radioactive Waste Management, 1987.

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Lochbaum, David A. Nuclear waste disposal crisis. PennWell Books, 1996.

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Holt, Mark. Civilian nuclear spent fuel temporary storage options. Congressional Research Service, Library of Congress, 1998.

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Book chapters on the topic "Final storage of radioactive waste"

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Merz, Erich R. "Biodegradation, a Non-Problem if Radioactive Raw Wastes are Properly Conditioned into a Final Solid Disposal Form?" In Microbial Degradation Processes in Radioactive Waste Repository and in Nuclear Fuel Storage Areas. Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5792-6_28.

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Fentiman, Audeen W. "Radioactive Waste Management radioactive radioactive waste management : Storage, Transport, Disposal." In Encyclopedia of Sustainability Science and Technology. Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4419-0851-3_29.

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Fentiman, Audeen W. "Radioactive Waste Management: Storage, Transport, Disposal." In Nuclear Energy. Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4614-5716-9_10.

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Lersow, Michael, and Peter Waggitt. "Final Disposal of Radioactive Waste with High Radioactivity (Heat-Generating Radioactive Waste)." In Disposal of All Forms of Radioactive Waste and Residues. Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-32910-5_7.

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Fentiman, Audeen W. "Radioactive Waste Management: Storage, Transport, and Disposal." In Encyclopedia of Sustainability Science and Technology. Springer New York, 2016. http://dx.doi.org/10.1007/978-1-4939-2493-6_29-3.

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Fentiman, Audeen W. "Radioactive Waste Management: Storage, Transport, and Disposal." In Nuclear Energy. Springer New York, 2018. http://dx.doi.org/10.1007/978-1-4939-6618-9_29.

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Pusch, Roland. "Introduction." In Geological Storage of Highly Radioactive Waste. Springer Berlin Heidelberg, 2008. http://dx.doi.org/10.1007/978-3-540-77333-7_1.

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Pusch, Roland. "The Geological Base for Developing and Assessing Concepts for HLW Disposal." In Geological Storage of Highly Radioactive Waste. Springer Berlin Heidelberg, 2008. http://dx.doi.org/10.1007/978-3-540-77333-7_2.

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Pusch, Roland. "The Rock." In Geological Storage of Highly Radioactive Waste. Springer Berlin Heidelberg, 2008. http://dx.doi.org/10.1007/978-3-540-77333-7_3.

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Pusch, Roland. "Engineered Barriers and Their Interaction with Rock." In Geological Storage of Highly Radioactive Waste. Springer Berlin Heidelberg, 2008. http://dx.doi.org/10.1007/978-3-540-77333-7_4.

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Conference papers on the topic "Final storage of radioactive waste"

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Thomson, Malcolm, and John Sims. "A Temporary Store for Radioactive Waste." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4719.

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To provide an efficient process for the final disposal of radioactive wastes, some nuclear sites are currently building suitable, temporary stores for such material. This paper describes the practical construction programme recently completed at a UK power reactor site under decommissioning. This site has a number of half height ISO containers filled with solid radioactive material that needed a temporary storage area before being consigned for final disposal. As a result, the site, Hunterston A Decommissioning Site, needed to construct some temporary radiation shield walls to contain the half
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Küppers, Christian, and Michael Sailer. "Fabrication of MOX Storage Rods for Direct Final Disposal As Method for Immobilisation of Surplus Plutonium." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1270.

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Abstract The German strategy of handling spent fuel was focussed on reprocessing since the 1960s although the German breeder projects are phased out since the late 1980s. Therefore, considerable plutonium was separated from German spent fuel and not reused. Some materials are not storable without periodical treatment and must be processed. The question arises whether a product can be fabricated that is also suitable for final disposal. Fabrication of “MOX storage rods” is considered to be the best treatment, especially under German conditions, for this purpose. This treatment can also reduce c
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Shadrack, Anthony, and Chang-Lak Kim. "Development of Disposal Option for Radioactive Waste." 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/icem2013-96370.

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The development of a lasting solution to radioactive waste management is a critical issue for future nuclear applications. When assessing radioactive waste disposal options factors such as volume of waste and sustainability of the plan must be considered. This paper describes basic plans for the disposal of Low- and intermediate-level radioactive wastes (LILW) expected to be generated from nuclear power plants for countries starting nuclear power program for the first time. The purpose of this paper was to develop a disposal option for Low- and intermediate level radioactive wastes for new com
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Sach, Udo, Goswin Schreck, Max Ritter, and Jean-Pierre Wenger. "High-Level-Waste and Spent Fuel Storage in Switzerland." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1173.

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Abstract At present, Switzerland has no final repository for radioactive wastes. Very early, the Swiss nuclear power plant operators were aware of the necessity to expand interim storage capacity for spent fuel elements and operational wastes. Already in 1991, Nordostschweizerische Kraftwerke AG (NOK) therefore started building a reactor-site interim storage facility (ZWIBEZ) at its Beznau power plant site. Moreover, as early as in 1990, “ZWILAG Zwischenlager Würenlingen AG”, a company established by the nuclear power plant operators had initiated the licensing procedure for a central interim
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Hoepfner, Uwe. "Final Covering of the Ronneburg Uranium Mining Site." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7190.

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The rehabilitation of WISMUT’s former Ronneburg uranium mining site involves backfilling of waste rock to the Lichtenberg open pit. The relocation project comprises about 110 million m3 of sulphide-bearing and AMD-generating waste rock which makes it the most important and most cost-intensive single surface restoration project conducted by WISMUT at the Ronneburg site. The backfilled waste rock has to be covered on an area of about 220 ha to control water infiltration and gas diffusion. Design planning for the final cover placement which began in 2004 had to be based on a comprehensive cost-be
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Ledebrink, F. W., and P. Faber. "Conditioning of Plutonium Waste for Long-Term Interim Storage." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1120.

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Abstract In the period since Germany’s experimental final repository ASSE was closed in 1978, around 5000 drums of conditioned plutonium-bearing radioactive waste from mixed-oxide (MOX) fuel fabrication have accumulated in the interim storage facilities of Siemens AG’s MOX fuel fabrication plant in Hanau, Germany — formerly ALKEM GmbH, now Siemens Decommissioning Projects (Siemens DP). Another 5000 drums will arise in the course of decommissioning and dismantling the MOX plant which has now been underway for some months. Hopes that a final waste repository would soon be able to go into operati
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Sokcic-Kostic, M., F. Langer, R. Schultheis, and Ch Klein. "Nuclear Fuel Assemblies and Fuel Debris Monitor for Characterization of Fuel Assemblies for Final Storage." 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/icem2013-96050.

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NUKEM monitor FAMOS is designed to measure the burn up of fuel assemblies (FA’s) and allows the calculation of the content of fissile material and other actinides. The knowledge of the isotopic composition and activities of FA’s is required for a safe handling and storage of the elements. The monitor analyses the measurement results on the basis of burn up calculations which improve the quality of the results, with respect to previous systems, which did not use those.
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Kövér, Miroslav, and Werner Stich. "The Waste Treatment Centre for Low- and Intermediate Waste (BSC - RAO) and Final Disposal of Conditioned Waste in Slovakia in Operation Since March 2000." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1124.

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Abstract On the site of the Slovak Nuclear Power Plant Bohunice a complete Waste Treatment Center for low and intermediate solid and liquid waste constructed. The facilities for volume reduction and further treatment are the incinerator, the high-force compactor and the evaporator. The facility for conditioning the waste is the cementation where the final product — filled concrete containers as the accepted waste package for long-term storage — is produced. The containers are transported to the Slovak Surface Repository for low and intermediate waste. Since March 2000, both projects are in hot
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Brennecke, Peter, Heinz Giller, Stefan Steyer, and Stefan Theis. "Quality Assurance in Radwaste Conditioning, Long-Term Interim Storage and Disposal in Germany." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1330.

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Abstract A nationwide harmonized quality assurance system for radwaste conditioning, interim storage and final disposal has been implemented in Germany. Up to now the guideline for all steps have been the waste acceptance criteria for the final disposal facilities Morsleben and Konrad. While the first one is in the stage of preparation for final closure the startup of the latter will be postponed for at least another 10 years. Possibly the next German repository will not be located at Konrad and start operation as late as 2030. This change in disposal policy has significant impact on the condi
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Sayenko, Sergey Yu, G. A. Kholomeyev, B. A. Shilyaev, et al. "Preparing the Spent Nuclear Fuel for Long-Term Storage and Final Disposal by Encapsulating It Into Glass-Ceramic Waste Forms." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1212.

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Abstract This paper describes the research work carried out at the NSC KIPT to develop and apply a final waste form in the shape of a monolithic solid block for the containment of spent nuclear fuel. To prepare radioactive waste for long-term storage and final deep geological disposal, investigations into the development of methods of immobilizing HLW simulators in protective solid matrices are being conducted at the NSC KIPT. For RBMK spent nuclear fuel it is proposed and justified to encapsulate the spent fuel bundles into monolithic protective blocks, produced with the help of hot isostatic
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Reports on the topic "Final storage of radioactive waste"

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Murty, K. L., and T. S. Elleman. A study of hydrogen effects on fracture behavior of radioactive waste storage tanks. Final report, October 1992--September 1994. Office of Scientific and Technical Information (OSTI), 1994. http://dx.doi.org/10.2172/296692.

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Sinha, A. K. Zircons and fluids: An experimental investigation with applications for radioactive waste storage. Final report, July 1, 1988--July 31, 1994. Office of Scientific and Technical Information (OSTI), 1998. http://dx.doi.org/10.2172/607519.

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Kunz, Daniel E. Radioactive waste storage issues. Office of Scientific and Technical Information (OSTI), 1994. http://dx.doi.org/10.2172/10178241.

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F.J. Bierich. Concepts for Waste Retrieval and Alternate Storage of Radioactive Waste. Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/859055.

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Caskey, G. R. Jr. Potential radiation damage: Storage tanks for liquid radioactive waste. Office of Scientific and Technical Information (OSTI), 1992. http://dx.doi.org/10.2172/10136608.

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Caskey, G. R. Jr. Potential radiation damage: Storage tanks for liquid radioactive waste. Office of Scientific and Technical Information (OSTI), 1992. http://dx.doi.org/10.2172/6668154.

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Anderson, M. T., D. C. Kunerth, and J. R. Davidson. Nondestructive examination technologies for inspection of radioactive waste storage tanks. Office of Scientific and Technical Information (OSTI), 1995. http://dx.doi.org/10.2172/114637.

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Siskind, B., D. R. Dougherty, and D. R. MacKenzie. Extended storage of low-level radioactive waste: potential problem areas. Office of Scientific and Technical Information (OSTI), 1985. http://dx.doi.org/10.2172/6044598.

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Rogers, R. D., M. A. Hamilton, R. H. Veeh, and J. W. Jr McConnell. Microbial degradation of low-level radioactive waste. Final report. Office of Scientific and Technical Information (OSTI), 1996. http://dx.doi.org/10.2172/261095.

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Henrie, J. O., D. J. Flesher, G. J. Quinn, and J. Greenborg. Hydrogen control in the handling, shipping, and storage of wet radioactive waste. Office of Scientific and Technical Information (OSTI), 1986. http://dx.doi.org/10.2172/6253113.

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