Abstract
Mining refers to the act of collecting ore containing a target metal from mines. This process generates gangue—rock that is commercially valueless and therefore subject to disposal. The process of extracting metal from its ore is called melting. Uraninite, pitchblend and brannerite are uranium containing ores, and they contain uranium in the form of oxide. Their grade generally ranges from 0.1 to 0.3 % triuranium octoxide (U3O8) equivalent. Although extracted ore of ordinary metals undergoes “dressing,” the process of separating valueless rocks based on physical or chemical characteristics by such methods as fire refining and aqueous refining, the dressing process is not effective for low-grade uranium ore. This kind of ore is crushed into pieces and dissolved in acid or alkali solution. Then uranium is refined and concentrated, followed by precipitation using strong alkali. An intermediate from this milling process is uranium concentrate, which is U3O8 powder, called yellow cake for its color. Its uranium content (U3O8 content) is about 70–80 %. This material is further refined (or purified) to increase purity and is converted to forms such as UF6, UO2 or metallic uranium, suitable for use as reactor fuel in the next process at fuel fabrication facilities. In this connection, refining means increasing the purity of metal resulting from melting by electrolysis or other processes; in the uranium melting process, purification corresponds to refining.
The nuclear regulatory system in Japan has been changed significantly after the Fukushima Daiichi Nuclear Power Station accident in March 2011. Descriptions in this chapter have been translated from the book originally published in Japanese before the accident, with minimal update where appropriate.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
References
Radioactive Waste Management Center, Current State of Research in Uranium Waste Treatment and Disposal, RWMC Topics, 26 (1993) (in Japanese)
Japan Nuclear Fuel Ltd., Japan Atomic Energy Agency, Global Nuclear Fuel – Japan Co., Ltd., Mitsubishi Nuclear Fuel Co., Ltd., Nuclear Fuel Industries, Ltd., and JCO Co., Ltd., Discussion Paper on Uranium Waste Disposal and Clearance (2006) (in Japanese)
Japan Atomic Energy Commission’s Advisory Committee on Nuclear Fuel-Cycle Backend Policy, Basic Policy on Uranium Waste Treatment and Disposal (2000) (in Japanese)
Nuclear Safety Commission of Japan, The Clearance Level for Uranium-handling Facilities (2009) (in Japanese)
Radioactive Waste Management Center, Changes in the Generation and Treatment of Waste from Nuclear Power Reactor Operation, RWMC Topics, No. 22 (1992) (in Japanese)
Japan Nuclear Energy Safety Organization, FY 2009 Annual Report on Nuclear Facility Operation and Management (2001), p. 707 (in Japanese)
T. Izumi, M. Hagiwara, T. Ohtsu, M. Tsujita, M. Arai, H. Inagawa and M. Nomi, Development of Radioactive Spent Ion-exchange Resin Treatment System, FAPIG, 174, 40–42, First Atomic Power Industry Group (2007) (in Japanese)
Thermal and Nuclear Power Engineering Society (ed.), Water and Chemical Management at Thermal and Nuclear Power Plants – VII. Management of Effluent, Waste Oil and Waste (Nuclear). Therm. Nucl. Power 58, 49–78 (2007) (in Japanese)
Nuclear Safety Division, Safe Environment Department, Fukui Prefectural Government, Operation and Construction Status of Power Plants for March-May 2010, Fukui Prefectural Panel on Nuclear Safety Management (2010) (in Japanese)
Radioactive Waste Management Center, Current State of Treatment, Storage and Disposal Technologies for Reprocessing Waste, RWMC Topics, 25 (1993) (in Japanese)
Radioactive Waste Management Center, Current State of TRU Waste Treatment, RWMC Topics, 34 (1995) (in Japanese)
Japan Nuclear Cycle Development Institute, FY 2002 Research and Development Subject Evaluation (Interim Evaluation) Report on the Evaluation Subject “Development of Krypton Recovery and Immobilization for Reprocessing Facilities,” JNC TN1440 2003–2005 (2003) (in Japanese)
T. Sakurai, A. Takahashi, Behavior of Iodine in the Reprocessing of Spent Nuclear Fuels (Research and Development), JAERI-Review 97–002 (1997) (in Japanese)
Radioactive Waste Management and Nuclear Facility Decommissioning Technology Center, Survey on Technologies for the Recycling of Resources Recovered from Radioactive Waste and Reduction of Associated Environmental Burdens Mainly through Nuclide Partitioning and Transmutation (2006) (in Japanese)
Japan Nuclear Cycle Development Institute, Technological Reliability of Geologic Disposal of High Level Radioactive Waste in Japan – Secondary Report on Geologic Disposal Research and Development (Summary Report), JNC TN1400 99–020 (1999) (in Japanese)
I. Fujii, Natural Reactor, (University of Tokyo Press, 1985) (in Japanese)
Japan Atomic Energy Agency, JAEA Activity Report, Material for the Fifth Meeting of the Working Group on Research Facility Waste, Committee on R&D in the Nuclear Energy Field, Ministry of Education, Culture, Sports, Science and Technology (May 12, 2009) (2009) (in Japanese)
Act on Final Disposal of Designated Radioactive Waste, June 7, 2000, Act No. 117 (2000) (in Japanese)
T. Mukoyama, Annihilation disposal of long-lived radioactive waste. Energy Rev. 14(2), 8 (1994) (in Japanese)
Y. Kondo, M. Kubota, T. Abe and K. Nagato, Development of a Group Partitioning Method: Method of Recovering and Using Useful Elements Contained in Spent Fuel (literature search), JAERI-M91-147, Japan Atomic Energy Research Institute (1991) (in Japanese)
Nuclear Energy Agency of the Organisation for Economic Co-operation and Development, Expert Group, A Status Report Accelerator-driven Systems (ADS) and Fast Reactors (FR) in Advanced Nuclear Fuel Cycles – A Comparative Study (2002)
Y. Morita, M. Kubota, Wet partitioning and waste treatment. Radioact. Waste Res. 2, 75 (1996) (in Japanese)
T. Nishimura, Y. Itamura, Toward realization of dry recycling technology and a metallic fuel FBR. Denchuken Rev. 37, 61 (2000) (in Japanese)
H. Oigawa, K. Nishihara, K. Minato, T. Kimura, Y. Arai, Y. Morita, S. Nakayama and J. Katakura, Current State and Future Policy on JAERI’s R&D of Partitioning and Transmutation Technology for Long-Lived Nuclides, JAERI-Review 2005–043, Japan Atomic Energy Research Institute (2005) (in Japanese)
Japan Atomic Energy Commission, Current State and Future Policy on R&D of Partitioning and Transmutation Technology (2009) (in Japanese)
LOI no 91–1381 du 30 décembre 1991 relative aux recherches sur la gestion des déchets radioactifs (91-1381/1991.12.30)
LOI no 2006–739 du 28 juin 2006 de programme relative á la gestion durable des matières et d_chets radioactifs (2006-739/2006.6.28)
Author information
Authors and Affiliations
Corresponding author
Editor information
Editors and Affiliations
Rights and permissions
Copyright information
© 2015 Authors
About this chapter
Cite this chapter
Okoshi, M., Nakayama, S. (2015). Generation and Characteristics of Radioactive Wastes. In: Nagasaki, S., Nakayama, S. (eds) Radioactive Waste Engineering and Management. An Advanced Course in Nuclear Engineering. Springer, Tokyo. https://doi.org/10.1007/978-4-431-55417-2_2
Download citation
DOI: https://doi.org/10.1007/978-4-431-55417-2_2
Publisher Name: Springer, Tokyo
Print ISBN: 978-4-431-55416-5
Online ISBN: 978-4-431-55417-2
eBook Packages: EngineeringEngineering (R0)