Skip to main content
SpringerLink
Log in

Radioactive Waste Management

  • Chapter
  • First Online:
Nuclear Fuel Cycle

Abstract

Radioactive wastes are generated during various stages of nuclear fuel cycle and their nature depends upon various factors such as its source of generation, type of fuel and its cladding material, process used in purification/fabrication of fuel, type of nuclear reactor, burnup of the fuel, off-reactor cooling period, process flow sheet used in SNF reprocessing and techniques adopted in decontamination/decommissioning. The present chapter describes the different types of radioactive wastes and the methodologies employed for their management.

Authors C. P. Kaushik and Kanwar Raj: Formerly at Nuclear Recycle Group, Bhabha Atomic Research Centre.

This is a preview of subscription content, log in via an institution to check access.

Access this chapter

Log in via an institution
Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 49.99
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 64.99
Price excludes VAT (USA)
  • Compact, lightweight edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info
Hardcover Book
USD 64.99
Price excludes VAT (USA)
  • Durable hardcover edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

References

  1. Predisposal management of radioactive waste. IAEA Safety Standards Series No. GSR-5 (2009)

    Google Scholar 

  2. Disposal of radioactive waste. IAEA Safety Standards Series No. SSR-5 (2011)

    Google Scholar 

  3. Management of radioactive waste. AERB Safety Code No. AERB/NRF/SC/RW (2007)

    Google Scholar 

  4. P.K. Wattal, Indian programme on radioactive waste management. Sadhana 38, 849–857 (2013)

    Article  Google Scholar 

  5. K. Raj, K.K. Prasad, N.K. Bandal, Radioactive waste management practices in India. Nucl. Eng. Des. 236, 914–930 (2006)

    Article  Google Scholar 

  6. P.K. Wattal, Backend of Indian nuclear fuel cycle—a road to sustainability. Prog. Nucl. Energy 101, 133–145 (2017)

    Article  Google Scholar 

  7. R. Natarajan, Reprocessing of spent nuclear fuel in India: present challenges and future programme. Prog. Nucl. Energy 101, 118–132 (2017)

    Article  Google Scholar 

  8. P.K. Dey, N.K. Bansal, Spent fuel reprocessing: a vital link in Indian nuclear power program. Nucl. Eng. Des. 236, 723–729 (2006)

    Article  Google Scholar 

  9. Handling and treatment of radioactive aqueous wastes. TECDOC No. 654, (IAEA, 1992)

    Google Scholar 

  10. Waste Treatment at La Hague and Marcoule Sites, Document No. ES/WM-49, ORNL, USA, pp. 2–9

    Google Scholar 

  11. P.D. Ozarde, S.K. Samanta, K. Raj, Management of intermediate level waste from past reprocessing using caesium specific resorcinol formaldehyde resin, in Proc of the IAEA Intl Conf on issues and trends in radioactive waste management. IAEA-CN-90/51 (2002)

    Google Scholar 

  12. K. Raj, C.P. Kaushik, R.K. Mishra, Radioactive waste management in U/Th fuel cycles, in Thoria-Based Nuclear Fuels, ed. by D. Das, S.R. Bharadwaj (Springer, London, 2013), pp. 357–358

    Google Scholar 

  13. Presented in lecture on “Management of Radioactive waste from reprocessing plants” in BRNS Theme Meeting on Status and Trends in Thermal Reactor Spent Fuel Processing in India, October 22, 2010

    Google Scholar 

  14. V.M. Efremenkov, Radioactive waste management at nuclear power plants, IAEA Bulletin, 4/1989, IAEA (1989), p. 38

    Google Scholar 

  15. Process Information, LERF & 200 Area ETF, Hanford Facility RCRA Permit Dangerous Waste Portion, Addendum C, p. C-67

    Google Scholar 

  16. New developments and improvements in processing of problematic radioactive waste. IAEA TECDOC No. 1579 (2007), p. 43

    Google Scholar 

  17. Fukushima Daiichi Accident, https://www.world-nuclear.org/information-library/safety-and-security/safety-of-plants/fukushima-daiichi-accident.aspx

  18. Overview of the multi-nuclide removal equipment (ALPS) at Fukushima Daiichi Nuclear Power Station, https://www.tepco.co.jp/en/nu/fukushima-np/handouts/2013/images/handouts_130329_01-e.pdf

  19. J. Braun, T. Barker, Fukushima Daiichi emergency water treatment. Nucl. Plant J. 36–37 (2012)

    Google Scholar 

  20. T. Tsukada et al., Early construction and operation of a highly contaminated water treatment system in Fukushima Daiichi Nuclear Power Station (I)—ion exchange properties of kurion herschelite in simulating contaminated water. J. Nucl. Sci. Technol. 51(2014)

    Google Scholar 

  21. C. Srinivas, G.S. Singh, A review study on organic waste management by green chemistry. Green Chem. Technol. Lett. 06, 4–13 (2020)

    Article  Google Scholar 

  22. Treatment and conditioning of radioactive organic liquids. Technical Report Series No. 656, IAEA (1992)

    Google Scholar 

  23. Predisposal management of organic radioactive waste. Technical report Series No. 427, IAEA (2004)

    Google Scholar 

  24. Handling and processing of radioactive waste from nuclear applications. IAEA Technical Report Series No. 402 (2001)

    Google Scholar 

  25. S. Manohar, C. Srinivas, T. Vincent, P.K. Wattal, Management of spent solvents by alkaline hydrolysis process. Waste Manage. 19, 509–517 (1999)

    Article  Google Scholar 

  26. K.K. Halder, K.V. Ravi, M.M. Malusare, Sanjay Kumar, Development and demonstration of vacuum distillation process for recovery of pure TBP and n dodecane from simulated organic liquid waste, BARC Newsletter, Jan–Feb (2018)

    Google Scholar 

  27. B.F. Judson, R.L. Moore, H.H. van Tuyl, R.W. Wirta, Chem. Eng. Symp. Ser. (A.I.Ch.E) vol. 55 (1959)

    Google Scholar 

  28. V. Kourim, J. Rais, B. Million, Exchange properties of complex cyanides-I: ion exchange of cesium on ferrocyanides. J. Inorg. Nucl. Chem. 26, 1111–1115 (1964)

    Article  Google Scholar 

  29. V.N. Ramonovsky, R&D activity on portioning in Russia, in fifth OECD/NEA information exchange meeting on actinides and fission product portioning and transmutation (SCK-CEN, Mol, Belgium, 1998)

    Google Scholar 

  30. V.N. Ramonovsky, Management of accumulated high level waste at the amyak production Association in the Russian Federation’ in issues and Trends in Radioactive waste management, in Proc. of international conference (IAEA, Vienna, 2003)

    Google Scholar 

  31. C.J. Pederson, The discovery of crown ethers. Science 241 (1988)

    Google Scholar 

  32. H. Gerow, G.E. Smith, M.W. Davis, Extraction of Cesium (+1) and Strontium (+2) from nitric acid solution using macrocyclic polyethers. Sep. Sci. Technol. 16, 519–548 (1981)

    Article  Google Scholar 

  33. J.W. McDowell, G.N. Case, Selective extraction of cesium from acidic nitrate solutions with didodecylnaphthalenesulfonic acid synergized with bis(tert-butylbenzo)-21-crown-7. Anal. Chem. 64 (1992)

    Google Scholar 

  34. S.R. Izatt, R.T. Hawkins, J.J. Christensen, R.M. Izatt, Cation transport from multiple alkali cation mixtures using a liquid membrane system containing a series of calixarene carriers. J. Am. Chem. Soc. 107 (1985)

    Google Scholar 

  35. Z. Asfari, C. Bressot, J. Vicens, C. Hill, J.F. Dozol, H. Rouquette, S. Eymard, V.L.B. Tournois, Doubly crowned calix[4]arenes in the 1,3-alternate conformation as cesium-selective carriers in supported liquid membranes. Anal. Chem. 67(18), 3133 (1995)

    Google Scholar 

  36. J.F. Dozol, N. Simon, V. Lamare, H. Rouquette, S. Eymard, B. Tournois, D. De Marc, R.M. Macias, A solution for cesium removal from high-salinity acidic or alkaline liquid waste: the crown calix[4]arenes. Sep. Sci. Technol. 34, 877–909 (1999)

    Google Scholar 

  37. M.A. Norato, M.H. Beasley, S.G. Campbell, A.D. Coleman, M.W. Geeting, J.W. Guthrie, C.W. Kennell, R.A. Pierce, R.C. Ryberg, D.D. Walker, J.D. Law, T.A. Todd, Demonstration of the caustic-side solvent extraction process for removing 137cs from high-level waste at savannah river site. Sep. Sci. Technol. 38, 2647–2666 (2003)

    Article  Google Scholar 

  38. P.V. Bonnesen, T.J. Haverlock, N.L. Engle, R.A. Sachleben, B.A. Moyer, Development of process chemistry for the removal of cesium from acidic nuclear waste by calix[4]arene-crown-6 ethers, in ACS Symposium Series 757, Calixarenes for Separations, ed. by G.J. Lumetta, R.D. Rogers, A.S. Gopalan (American Chemical Society, Washington, DC, 2000)

    Google Scholar 

  39. P.S. Dhami et al., Studies on the development of a two stage SLM system for the separation of carrier‐free 90Y using KSM‐17 and CMPO as carriers. Sep. Sci. Technol. 42(Issue 5) (2007)

    Google Scholar 

  40. M. Blicharska, B. Bartoś, S. Krajewski, A. Bilewicz, Separation of fission produced 106Ru from simulated high level nuclear wastes for production of brachytherapy sources. J. Radioanal. Nucl. Chem. (2013)

    Google Scholar 

  41. G.P. Salvatores, Radioactive waste partitioning and transmutation within advanced fuel cycles: achievements and challenges. Prog. Part. Nucl. Phys. 66, 144–166 (2011)

    Article  Google Scholar 

  42. M. Salvatores, Partitioning and transmutation of spent nuclear fuel and radioactive waste, in Nuclear Fuel Cycle Science and Engineering (Woodhead Publishing Series in Energy, 2012), pp. 501–530

    Google Scholar 

  43. S. Tachimori, Y. Morita, Overview of solvent extraction chemistry for reprocessing. Ion Exch. Solvent Extr. Ser. Adv. 19, 1–64 (2009)

    Google Scholar 

  44. K.L. Nash, J.C. Braley, Chemistry of radioactive materials in the nuclear fuel cycle, in Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment (Woodhead Publishing Series in Energy, 2011), pp. 3–22

    Google Scholar 

  45. Paulenova, Physical and chemical properties of actinides in nuclear fuel reprocessing, in Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment (Woodhead Publishing Series in Energy, 2011), pp. 23–57

    Google Scholar 

  46. Hill, Development of highly selective compounds for solvent extraction processes: partitioning and transmutation of long-lived radionuclides from spent nuclear fuels, in Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment (Woodhead Publishing Series in Energy, 2011), pp. 311–362

    Google Scholar 

  47. Hill, Overview of recent advances in An(III)/Ln(III) separation by solvent extraction. Ion Exch. Solvent Extr. Ser. Adv. 19, 119–194 (2009)

    Google Scholar 

  48. K.L. Nash, The chemistry of TALSPEAK: a review of the science. Solvent Extr. Ion Exch. 33, 1–55 (2015)

    Article  Google Scholar 

  49. M. Nilsson, K.L. Nash, A review of the development and operational characteristics of the TALSPEAK process. Solvent Extr. Ion Exch. 25, 665–701 (2007)

    Article  Google Scholar 

  50. C.A. Sharrad, D.M. Whittaker, The use of organic extractants in solvent extraction processes in the partitioning of spent nuclear fuels, in Reprocessing and Recycling of Spent Nuclear Fuel (Woodhead Publishing Series in Energy, 2015), pp. 153–189

    Google Scholar 

  51. G. Modolo, A. Geist, M. Miguirditchian, Minor actinide separations in the reprocessing of spent nuclear fuels: recent advances in Europe, in Reprocessing and Recycling of Spent Nuclear Fuel (Woodhead Publishing Series in Energy, 2015), pp. 245–287. https://doi.org/10.1016/B978-1-78242-212-9.00010-1

  52. B.A. Moyer, G.J. Lumetta, B.J. Mincher, Minor actinide separation in the reprocessing of spent nuclear fuels: recent advances in the United States, in Reprocessing and Recycling of Spent Nuclear Fuel (Woodhead Publishing Series in Energy, 2015), pp. 289–312. https://doi.org/10.1016/B978-1-78242-212-9.00011-3

  53. S. Manohar, V.P. Patel, U. Dani, M.R. Venugopal, P.K. Wattal, Engineering scale demonstration facility for actinide partitioning of high level waste, BARC Newsletter 332, May–June (2013) 13–18

    Google Scholar 

  54. S. Manohar, V.P. Patel, U. Dani, M.R. Venugopal, P.K. Wattal, hot commissioning of an actinide separation demonstration facility, BARC Newsletter Founder’s Day Special Issue (2015) 237–246

    Google Scholar 

  55. C.P. Kaushik, Amar Kumar, N.S. Tomar, S. Wadhwa, D. Mehta, R.K. Mishra, J. Diwan, S. Babu, S.K. Marathe, A.P. Jakhete, S. Jain, A. Gangadharan, K. Agarwal, Recovery of cesium from high level liquid radioactive waste for societal application: an important milestone, BARC Newsletter, March-April (2017) 3–4

    Google Scholar 

  56. K. Raj, C.P. Kaushik, Glass matrices for vitrification of radioactive waste—an update on R&D efforts, in IOP Conference Series: Materials Science and Engineering

    Google Scholar 

  57. Design and operation of high level waste vitrification and storage facilities. Technical Report Series No. 333 (IAEA, Vienna)

    Google Scholar 

  58. W. Baehr, Industrial vitrification processes for high-level liquid waste solutions, IAEA Bull. 4 (1989)

    Google Scholar 

  59. R.D. Quang, E. Pluche, C. Ladirat, A. Prod’Homme, review of the French vitrification program, in WM’04 Conference, February 29-March 4 (Tucson, AZ, 2004)

    Google Scholar 

  60. D.J. Bradley, K.J. Schneider, Radioactive waste management in the USSR: a review of unclassified sources, 1963–1990. PNL Report No. 7182 (Pacific Northwest Laboratory Richland, Washington), p 99352

    Google Scholar 

  61. T. Harrison, Vitrification of high level waste in the UK, in 2nd International Summer School on Nuclear Glass Waste form: Structure, Properties and Long Term Behavior, SumGLASS 2013, Procedia Materials Science, vol. 7 (2014), pp. 10–15

    Google Scholar 

  62. G. Suneel et al., Experimental investigation and numerical modelling of a joule-heated ceramic melter for vitrification of radioactive waste. J. Hazard. Toxic Radioact. Waste 23 (2019)

    Google Scholar 

  63. L. Luezzi, Th. M. Nieuwenhuizen, Thermodynamics of the Glassy State (CRC Press, 2007)

    Google Scholar 

  64. A.K. Varshneya, Fundamentals of Inorganic Glasses: Society of Glass Technology (Sheffield, UK, 2006)

    Google Scholar 

  65. D.R. Uhlmann, A kinetic treatment of glass formation. J. Non-Cryst. Solids 7, 337–348 (1972)

    Article  Google Scholar 

  66. M.I. Ojovan, W.E. Lee, New Developments in Glassy Nuclear Wasteforms (Nova Science Publishers Inc., New York, 2007)

    Google Scholar 

  67. M.I. Ojovan, W.E. Lee, An Introduction to Nuclear Waste Immobilization (Elsevier, Oxford, UK, 2005)

    Google Scholar 

  68. C.P. Kaushik, Indian programme for vitrification of high level radioactive liquid waste. Proc. Mater. Sci. 7 (2014)

    Google Scholar 

  69. C.C. Chapman, Nuclear waste glass melter design including the process and control systems. IEEE Trans. Ind. Appl. IA-18(1) (1982)

    Google Scholar 

  70. S. Weisenburger, Nuclear waste vitrification in a ceramic lined electric glass melter. IEEE Trans. Ind. Appl. IA-18 (1982)

    Google Scholar 

  71. D. Gombert, J.R. Richardson, Cold crucible induction melter design and development. Nucl. Technol. 141 (2003)

    Google Scholar 

  72. G. Sugilal, A. Thess, G. Weidmann, U. Lange, Chaotic mixing in a Joule-heated glass melt. Phys. Fluids 22 (2010)

    Google Scholar 

  73. G. Sugilal, Experimental analysis of the performance of cold crucible induction glass melter. Appl. Therm. Eng. 28 (2008)

    Google Scholar 

  74. R.D. Quang, V. Petitjean, F. Hollebecque, O. Pinet, T. Flament, A. Prod’homme, Vitrification of HLW produced by uranium/molybdenum fuel reprocessing in COGEMA’s cold crucible melter, in Proc. Waste Management Symposium (Tucson, USA, 2003)

    Google Scholar 

  75. R.A. Day, J. Ferenczy, E. Drabarek, T. Advocat, C. Fillet, J. Lacombe, C. Ladirat, C. Veyer, R. Do Quang, J. Thomasson, Glass-ceramic in a cold crucible melter: the optimum combination for greater waste processing efficiency, in Proc. Waste Management Symposium (Tucson, USA, 2003)

    Google Scholar 

  76. Jouan, R. Boen, S. Merlin, P. Roux, A warm heart in a cold body—melter technology for tomorrow, in: Proceedings of the Spectrum 96, International Topical Meeting on Nuclear and Hazardous Waste Management (Seattle, USA, 1996)

    Google Scholar 

  77. F.A. Lifanov, I.A. Sobolov, S.A. Dimitriev, S.V. Stefanovsky, Vitrification of low and intermediate level waste: technology and glass performance, in Proc. Waste Management Symposium (Arizona, USA, 2004)

    Google Scholar 

  78. R. Didierlaurent, E. Chauvin, J. Lacombe, C. Mesnil, C. Veyer, Cold crucible deployment in La Hague facility: the feedback from the first four years of operation, in Proc. Waste Management Symposium (Arizona, USA, 2015)

    Google Scholar 

  79. S.V. Stefanovsky, A.G. Ptashkin, I.A. Knyazev, O.I. Stefanovsky, S.V. Yudintsev, B.S. Nikonov, B.F. Myasoedov, Cold crucible melting and characterization of titanate-zirconate pyrochlore as a potential rare earth/actinide waste form. Ceram. Int. 45(2019)

    Google Scholar 

  80. C.P. Kaushik et al., Barium borosilicate glass—a potential matrix for immobilization of sulfate bearing high-level radioactive liquid waste. J. Nucl. Mater. 358(2–3), 129–138 (2006)

    Article  Google Scholar 

  81. Classification of radioactive waste. IAEA-TECDOC-1744 (Vienna, 2009)

    Google Scholar 

  82. Management of radioactive waste. Atomic Energy Regulatory Board, DAE, India. Safety Guide AERB/NPP/SG/O-11 (Mumbai, 2009)

    Google Scholar 

  83. Radioactive waste management technology, in Chapter 7: Gaseous Radioactive Wastes (USNRC Technical Training Center), Rev. 0311

    Google Scholar 

  84. Air filters for use at nuclear facilities. IAEA TRS No-122 (1970)

    Google Scholar 

  85. Treatment and conditioning of the radioactive solid wastes. IAEA TECDOC-655 (Vienna, 1992)

    Google Scholar 

  86. R. Vanbrabant, J. Deckers, P. Luycx, M. Detilleux, P. Beguin, 40 years of experience in incineration of radioactive waste in Belgium, IAEA-CSP-6/C (2001)

    Google Scholar 

  87. K.C. Pancholi, Suprabha, S. Agarwal, S.K. Solankar, S. Bhandari, S.K. Mishra, S. Ghorui, N.S. Tomar, R.L. Bhardwaj, E. Kandaswamy, M. Martin, A. Sharma, C.P. Kaushik, Plasma pyrolysis and incineration for low level radioactive solid wastes. BARC News Lett. Nov-Dec (2020) 6–10

    Google Scholar 

  88. M. Ternovykh, G. Tikhomirov, I. Saldikov, A. Gerasimov, Decay heat power of spent nuclear fuel of power reactors with high burnup at long-term storage, in EPJ Web of Conferences, vol. 153 (2017)

    Google Scholar 

  89. H.G. Zhao, H. Shao, H. Kunz, J. Wang, R. Su, Y.M. Liu, Numerical analysis of thermal process in the near field around vertical disposal of high-level radioactive waste. J. Rock Mech. Geotech. Eng. 6, 55–60 (2014)

    Article  Google Scholar 

  90. P.D. Ozarde, K.K. Haldar, S. Sarkar, Interim storage of vitrified high-level radioactive waste. Indian Nucl. Soc. News 5, 29–32 (2008)

    Google Scholar 

  91. K. Deepa, A.K. Jakhate, D. Mehta, N.S. Tomar, C.P. Kaushik, K.M. Singh, Estimation of heat generation in vitrified waste product and shield thickness for transportation of vitrified waste product using Monte Carlo techniques. Indian J. Pure Appl. Phys. 50, 867–886 (2012)

    Google Scholar 

  92. Interim storage of radioactive waste packages. Technical Reports Series No. 390 (International Atomic Energy, Vienna, 1998), pp. 54–55

    Google Scholar 

  93. https://radioactivity.eu.com/radioactive_waste/is_vitrified_waste

  94. https://www.power-technology.com/analysis/featureuk-nuclear-waste-where-its-generated-contained-transported-and-stored (2020)

  95. B. Faybishenko, J. Birkholzer, D. Sassani, P. Swift, Geological challenges in radioactive waste isolation: Fifth worldwide review (2016)

    Google Scholar 

  96. R.K. Narayan, R.K. Bajpai, Deep geological repositories for vitrified high level long lived wastes, in Bulletin of Indian Association of Nuclear Chemists and Allied Scientists, vol. 6 (2007), pp. 224–245

    Google Scholar 

  97. D. Savage, The Scientific and Regulatory Basis for the Geological Disposal of Radioactive Waste (Wiley, 1995), pp. 1–64

    Google Scholar 

  98. Scientific and technical basis for the near surface disposal of low and intermediate level waste. Technical Reports Series No. 412 (2002)

    Google Scholar 

  99. Near surface disposal facilities for radioactive waste. IAEA Safety Standards Series No. SSG-29 (2014)

    Google Scholar 

  100. Siting of near surface disposal facilities. IAEA Safety Series No. 111-G-3.1 (1994)

    Google Scholar 

  101. Monitoring and surveillance of radioactive waste disposal facilities. Specific Safety Guides No. SSG-31 (2014)

    Google Scholar 

  102. J.H. Coobs, J.R. Gissel, History of disposal of radioactive wastes into the ground at Oak Ridge National Laboratory. No. ORNL/TM-10269 (Oak Ridge National Lab., TN USA, 1986)

    Google Scholar 

  103. E.R. Vance, B.D. Begg, D.J. Gregg, Geological repository systems for safe disposal of spent nuclear fuels and radioactive waste, in Chapter 10—Immobilization of High-Level Radioactive Waste and Used Nuclear Fuel for Safe Disposal in Geological Repository Systems, 2nd edn. (WP, 2017), pp. 269–295

    Google Scholar 

  104. Geological disposal facilities for radioactive waste. Safety Requirements No. WS-R-4 (Vienna, 2006)

    Google Scholar 

  105. Geological disposal facilities for radioactive waste. Specific Safety Guide No. SSG-14 (Vienna, 2011)

    Google Scholar 

  106. Planning and design considerations for geological repository programmes of radioactive waste. IAEA-TECDOC-1755. (IAEA, Vienna, 2014)

    Google Scholar 

  107. R.P. Rechard, Historical background on performance assessment for the waste isolation pilot plant. Reliab. Eng. Syst. Saf. 69, 5–46 (2000)

    Article  Google Scholar 

  108. J. Birkholzer, J. Houseworth, C. Tsang, Geologic disposal of high-level radioactive waste: status, key issues, and trends. Annu. Rev. Environ. Resour. 37, 79–106 (2012)

    Google Scholar 

  109. P. Sellin, O.X. Leupin, the use of clay as an engineered barrier in radioactive waste management—a review. Clays Clay Miner. 61, 477–498 (2013)

    Article  Google Scholar 

  110. D.G. Bennett, G. Sallfors, SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU—engineered barriers, engineering geology and chemical inventory. Initial review phase. Report number: 2016:12. ISSN: 2000-0456

    Google Scholar 

  111. M. Buser, K. Verfassen, Repositories for low and intermediate level radioactive waste in Sweden and Finland: a travel report (2019)

    Google Scholar 

Further Reading

  1. Handling and processing of radioactive waste from nuclear applications. Technical Report Series No. 402 (IAEA, 2001)

    Google Scholar 

  2. Modular design of processing and storage facilities for small volumes of low and intermediate level radioactive waste including disused sealed sources. IAEA Nuclear Energy Series, NW-T-1.4 (IAEA, 2014)

    Google Scholar 

  3. Management of radioactive waste from the mining and milling of ores. Safety Guide, WS-G-1.2 (IAEA, 2010)

    Google Scholar 

  4. Combined methods for liquid radioactive waste treatment. IAEA TECDOC No. 1336 (IAEA, 2003)

    Google Scholar 

  5. Application of ion exchange processes for treatment of radioactive waste and management of spent ion exchangers. Technical Report Series No. 408 (IAEA, 2002)

    Google Scholar 

  6. Predisposal management of radioactive waste from nuclear power plants and research reactors. IAEA Safety Standards Series No. SSG-40 (IAEA, 2016)

    Google Scholar 

  7. Predisposal management of radioactive waste from nuclear fuel cycle facilities. IAEA Safety Standards Series No. SSG-41 (IAEA, 2016)

    Google Scholar 

  8. Application of membrane technologies for liquid radioactive waste processing. Technical Report Series No. 431 (IAEA, 2004)

    Google Scholar 

  9. Chemical precipitation processes for treatment of aqueous radioactive waste. Technical Report Series No. 337 (IAEA, 1992)

    Google Scholar 

  10. Predisposal management of low and intermediate level radioactive waste. Document No. AERB/NRF/SG/RW-2 (AERB, 2007)

    Google Scholar 

  11. Management of radioactive wastes arising during operation of PHWR based NPPS. Document No. AERB/NPP/SG/O-11 (AERB, 2004)

    Google Scholar 

  12. Liquid and solid radwaste management in pressurized heavy water reactor based nuclear power plants. Document No. AERB/SG/D-13 (AERB, 2002)

    Google Scholar 

  13. Hazardous and Radioactive Waste Treatment Technologies Handbook, ed. by C.H. Oh (CRC Press, 2001)

    Google Scholar 

  14. Radioactive Waste Engineering and Management, ed. by S. Nagasaki, S. Nakayama (Springer, 2015)

    Google Scholar 

  15. Handbook of Advanced Radioactive Waste Conditioning Technologies, ed. by M. Ojovan (Elsevier, 2011)

    Google Scholar 

  16. M.I. Ojovan, W.E. Lee, S.N. Kalmykov, An Introduction to Nuclear Waste Immobilization

    Google Scholar 

  17. International Atomic Energy Agency, implications of partitioning & transmutation in radioactive waste. Technical Report Series No. 435 (2004)

    Google Scholar 

  18. International Atomic Energy Agency, Assessment of partitioning processes for transmutation of actinides. IAEA TECDOC No. 1648 (2010)

    Google Scholar 

  19. RED-IMPACT: Impact of Partitioning, Transmutation and Waste Reduction Technologies on the Final Nuclear Waste Disposal (2008)

    Google Scholar 

  20. Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment (Woodhead Publishing Series in Energy, 2011)

    Google Scholar 

  21. Reprocessing and Recycling of Spent Nuclear Fuel (Woodhead Publishing Series in Energy, 2015)

    Google Scholar 

  22. Ion Exch. Solvent Extr. Ser. Adv. 19 (2009)

    Google Scholar 

  23. T. Fanghänel et al., Transuranium elements in the nuclear fuel cycle, in Handbook of Nuclear Engineering (2010), pp. 2935–2998

    Google Scholar 

  24. B. Bonin, The scientific basis of nuclear waste management, in Handbook of Nuclear Engineering (2010), pp. 3253–3419

    Google Scholar 

  25. J. VeliscekCarolan, Separation of actinides from spent nuclear fuel: a review. J. Hazard. Mater. 318, 266 (2016)

    Article  Google Scholar 

  26. R.F. Taylor, Chemical engineering problems of radioactive waste fixation by vitrification. Chem. Eng. Sci. 40(4) (1985)

    Google Scholar 

  27. J.A.C. Marples, The preparation, properties, and disposal of vitrified high level waste from nuclear fuel reprocessing. Glass Technol. 29(6) (1988)

    Google Scholar 

Download references

Author information

Authors and Affiliations

  1. Nuclear Recycle Group, Bhabha Atomic Research Centre, Mumbai, 400085, India

    Smitha Manohar, G. Sugilal, R. K. Bajpai, C. P. Kaushik & Kanwar Raj

Authors
  1. Smitha Manohar
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. G. Sugilal
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. R. K. Bajpai
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. C. P. Kaushik
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. Kanwar Raj
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Smitha Manohar .

Editor information

Editors and Affiliations

  1. Homi Bhabha National Institute, Anushaktinagar, Mumbai, Maharashtra, India

    B. S. Tomar

  2. Formerly Homi Bhabha National Institute, Anushaktinagar, Mumbai, Maharashtra, India

    P. R. Vasudeva Rao

  3. Formerly Chemical Engineering Group, Bhabha Atomic Research Centre, Mumbai, Maharashtra, India

    S. B. Roy

  4. Formerly Advanced Fuel Fabrication Facility, Bhabha Atomic Research Centre, Mumbai, Maharashtra, India

    Jose P. Panakkal

  5. Formerly Nuclear Recycle Group, Bhabha Atomic Research Centre, Mumbai, Maharashtra, India

    Kanwar Raj

  6. Formerly Radiological Safety Division, Atomic Energy Regulatory Board, Mumbai, Maharashtra, India

    A. N. Nandakumar

Rights and permissions

Reprints and permissions

Copyright information

© 2023 The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

About this chapter

Check for updates. Verify currency and authenticity via CrossMark

Cite this chapter

Manohar, S., Sugilal, G., Bajpai, R.K., Kaushik, C.P., Raj, K. (2023). Radioactive Waste Management. In: Tomar, B.S., Rao, P.R.V., Roy, S.B., Panakkal, J.P., Raj, K., Nandakumar, A.N. (eds) Nuclear Fuel Cycle. Springer, Singapore. https://doi.org/10.1007/978-981-99-0949-0_8

Download citation

  • DOI: https://doi.org/10.1007/978-981-99-0949-0_8

  • Published:

  • Publisher Name: Springer, Singapore

  • Print ISBN: 978-981-99-0948-3

  • Online ISBN: 978-981-99-0949-0

  • eBook Packages: EnergyEnergy (R0)

Publish with us

Policies and ethics

Search

Navigation