Radioactive Waste Management

  • P. A. Baisden
  • C. E. Atkins-Duffin


Issues related to the management of radioactive wastes are presented with specific emphasis on high-level wastes generated as a result of energy and materials production using nuclear reactors. The final disposition of these high-level wastes depends on which nuclear fuel cycle is pursued, and range from once-through burning of fuel in a light water reactor followed by direct disposal in a geologic repository to more advanced fuel cycles (AFCs) where the spent fuel is reprocessed or partitioned to recover the fissile material (primarily 235U and 239Pu) as well as the minor actinides (MAs) (neptunium, americium, and curium) and some long-lived fission products (e.g., 99Tc and 129I). In the latter fuel cycle, the fissile materials are recycled through a reactor to produce more energy, the short-lived fission products are vitrified and disposed of in a geologic repository, and the minor actinides and long-lived fission products are converted to less radiotoxic or otherwise stable nuclides by a process called transmutation. The advantages and disadvantages of the various fuel cycle options and the challenges to the management of nuclear wastes they represent are discussed.


Fission Product Fuel Cycle Spend Fuel Nuclear Fuel Cycle Minor Actinide 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.



The authors would like to thank Prof. W. F. Kinard and Dr. W.G. Halsey for their insightful comments made during the preparation of the manuscript. The authors also gratefully acknowledge the technical editing efforts of Ms. D. Schliech and Ms. K. Ramirez for their careful attention to detail in preparing this document in the proper camera-ready format. This work was performed under the auspices of the US Department of Energy by the Lawrence Livermore National Laboratory under Contract No. W-7405-Eng-48.


  1. Albright D (1993) World inventory of plutonium and highly enriched uranium, 1992. Oxford University Press, New YorkGoogle Scholar
  2. Albright D, Berkhout F, Walker W (1997) Plutonium and highly enriched uranium 1996: world inventories, capabilities, and policies. Oxford University Press, New YorkGoogle Scholar
  3. ANL-99/15 (1999) A technology roadmap for developing ATW technology, Separations and waste form technology, September 1999Google Scholar
  4. Beller D, Rhodes R (2000) The need for nuclear power. Foreign Affairs 79:30CrossRefGoogle Scholar
  5. Benedict M, Pigford T, Levi HW (1981) Nuclear chemical engineering, 2nd edn. McGraw Hill, New YorkGoogle Scholar
  6. Chartier D, Donnet L, Adnet JM (1998) Radiochimica Acta 83(3):129Google Scholar
  7. Chen J, Zhu Y, Jiao R (1996) Sep Sci Technol 31:2723CrossRefGoogle Scholar
  8. Choppin GR, Rydberg J (1980) Nuclear chemistry, theory and applications. Pergamon, OxfordGoogle Scholar
  9. Choppin GR, Rydberg J, Liljenzin JO (1995) Radiochemistry and nuclear chemistry, theory and applications. Butterworth-Heinemann, Great BritainGoogle Scholar
  10. Coops MM, Knighton JB, Mullins LJ (1983) Pyrochemical processing of plutonium. In: Carnall WT, Choppin GR (eds) Plutonium chemistry, ACS symposium series, vol 216. American Chemical Society, Washington DC, pp 381–400Google Scholar
  11. Cuillerdier C, Musikas C, Hoel P, Nigond L, Vitart X (1991) Sep Sci Technol 26(9):1229CrossRefGoogle Scholar
  12. Culler FL (1956) Reprocessing of reactor fuel in blanket materials by solvent extraction. In: Bruce FR, Flecther IM, Hyman HH, Katz KJ (eds) Process chemistry, Progress in nuclear energy, Series III, Vol 1. McGraw Hill, New York, pp 172–194Google Scholar
  13. DOE (2001) United States Department of Energy, Office of Nuclear Energy, Science and Technology and Coordinated with the National Nuclear Security Administration. Report to Congress — The Advanced Accelerator Applications Program Plan, US Government Printing Office, Washington DCGoogle Scholar
  14. DOE/RW-0519 (1999) A roadmap for developing accelerator transmutation of waste (ATW) technology, A report to congress, October 1999Google Scholar
  15. Donnet L, Adnet JM, Faure N, Bros P, Brossard Ph, Josso F, (1999) The development of the SESAME process. In: Proceedings of the fifth OECD/NEA information exchange meeting on actinide and fission product partitioning and transmutation, Mol, Belgium, 25–27 November 1998Google Scholar
  16. Dozol JF, Dozol M, Macias RM (2000) J Incl Phenom Macro Chem 38(1–4):1CrossRefGoogle Scholar
  17. Ensor DD, Jarvinen GD, Smith BF (1988) Solv Extr Ion Exch 6:439CrossRefGoogle Scholar
  18. Esimantovskii VM, Galkin BY, Lazarev LN, Lyubtsev RI, Romanovski VN, Shishkin DN (1992) Technological tests of HAW partitioning with the use of chlorinated cobalt dicarbolyde (CHCODIC), Management of secondary wastes. In: Post RG (es) Proceedings of the symposium on waste management, Arizona Board of Regents, Tuscon, pp 801–804Google Scholar
  19. Horwitz EP, Schulz WW (1999) Solvent extraction in the treatment of acidic high-level liquid waste: where do we stand? In: Bond AH, Dietz ML, Rogers RD (eds) Metal ion separation and preconcentration: progress and opportunities, ACS symposium series, vol 716, American Chemical Society, Washington DC, pp 20–50CrossRefGoogle Scholar
  20. Horwitz EP, Dietz ML, Fisher DE (1990) Solv Extr Ion Exch 8:557CrossRefGoogle Scholar
  21. Horwitz EP, Dietz ML, Fisher DE (1991) Solv Extr Ion Exch 9:1CrossRefGoogle Scholar
  22. International Atomic Energy Agency (IAEA) (1977) Regional nuclear fuel cycle centres, Vienna, AustriaGoogle Scholar
  23. Jain S, Ramaswamy M, Theyyunni TK (1995) Removal of strontium from low level waste using zeolite 4A. In: NUCAR 95: proceedings of the nuclear and radiochemistry symposium, Kalpakkam, India, 21–24 February 1995Google Scholar
  24. Jarvinen GD, Marsh SF, Smith BF, Yarbro SL, Yates M, Walker RB (1992) Baseline actinide blanket processing flowsheet for the ATW program, LA-UR-92-63, Los Alamos National Laboratory, Los AlamosGoogle Scholar
  25. Kolarik E, Koch G, Kuesel HH, Fritsch J (1972) Separation of Americium and Curium from highly radioactive waste solution, KFK-1553, Karlsruhe Nuclear Research Center, Karlsruhe, GermanyGoogle Scholar
  26. Kumar A, Mohapatra PK, Pathak PN, Manchanda VK (1997) Dicyclohexano 18 Crown 6 in butanol-octanol mixture: a promising extractant of Sr(II) from nitric acid medium. Talanta 4:387CrossRefGoogle Scholar
  27. LANL (1999) Roadmap for the development of accelerator transmutation of waste: target and blanket systemGoogle Scholar
  28. Liljenzin JO, Persson G, Svantesson I, Wingefors S (1984) Radiochimica Acta 35:155Google Scholar
  29. Madic C (2000) Overview of the hydrometallurigcal and pyro-metallurgical processes studied worldwide for the partitioning of high active nuclear wastes in actinide and fission partitioning and transmutation, Madrid, OECD/NEAGoogle Scholar
  30. Madic C, Hudson MJ, Liljenzin JO, Glatz JP, Nannicini R, Facchini A, Kolarik Z, Odoj R (2000) New partitioning techniques for minor actinides, Final Report, EUR 19149Google Scholar
  31. Mathur JN, Murali MS, Iyer RH, Ramunujam A, Dhami PS, Gopalakrishnan V, Rao MK, Badheka LP, Banerji A (1995) Nucl Technol 109:219Google Scholar
  32. Mathur JN, Murali MS, Nash KL (2001) Solv Extr Ion Exch 19(3):357CrossRefGoogle Scholar
  33. Morita Y, Tani S, Kubota M (1991) Separation of transuranic elements from high-level waste by extraction with diisodecyl phosphoric acid. In: The third international conference on nuclear fuel reprocessing and waste management, Recod’91, Vol 1, Sendai, JapanGoogle Scholar
  34. Musikas C (1984) Actinide-lanthanide group separation using sulfur and nitrogen donor extractants. In: International chemistry congress of Pacific Basin societies, CEA-Conf-7706, HonoluluGoogle Scholar
  35. Musikas C (1985) Actinide/lanthanide group separation using sulphur, and nitrogen donor extractants. In: Choppin GR, Navratil JD, Shulz WW (eds) Actinide/lanthanide separations, World Scientific, Philadelphia, pp 19–30Google Scholar
  36. Musikas C (1999) Review of possible technologies for actinide separations using other extractants than TBP, NATO SCI. Ser., Ser. 2 53, Chemical Separation Technologies and Related Methods of Nuclear Waste Management, pp 99–122Google Scholar
  37. Musikas C, Hubert H (1987) Solv Extr Ion Exch 5:877CrossRefGoogle Scholar
  38. NAS (1957) The disposal of radioactive waste on land. National Academy PressGoogle Scholar
  39. NAS (1994) Management and disposal of excess weapons plutonium. National Academy of Sciences. Committee on International Security and Arms Control, National Academy Press, Washington DC, p 34Google Scholar
  40. NAS (1996) Nuclear wastes, technologies for separations and transmutation. National Academy PressGoogle Scholar
  41. NAS (2000) Electrometallurgical techniques for DOE spent fuel – final report. National Academy PressGoogle Scholar
  42. OCED/NEA (1999) Actinide and fission product partitioning and transmutation proceedings of the fifth international information exchange meeting, Mol, Belgium, 25–27 November 1998Google Scholar
  43. OCED/NEA (2001) Actinide and fission product partitioning and transmutation sixth international information exchange meeting, Madrid, Spain, 11–13 December 2000Google Scholar
  44. OECD/NEA (1998) Status and assessment report of actinide and fission product partitioning and transmutation, OECD Report NEA/PTS/DOCGoogle Scholar
  45. OECD/NEA (2000) Nuclear energy agency, Organisation for ecomomic co-operation and development. Actinide and fission product partitioning and transmutation, NEA Press, ParisGoogle Scholar
  46. OECD/NEA (2002) Accelerator-driven systems (ADS) and fast reactors (FR). In: Advanced nuclear fuel cycles: a comparative study, NEA Press, ParisGoogle Scholar
  47. Persson G, Wingefors S, Liljenzin JO, Svantesson I (1984) Radiochimica Acta 35:163Google Scholar
  48. Persson G, Svantesson S, Wingefors S, Liljenzin JO (1986) Solv Extr Ion Exch 2:89CrossRefGoogle Scholar
  49. Raisbeck GM, Yiou F, Zhou ZQ, Kilius LR (1995) J Marine Syst 6(N5-6):561CrossRefGoogle Scholar
  50. Schulz WW, Horwitz EP (1988) Sep Sci Technol 23:1191CrossRefGoogle Scholar
  51. Selucky P, Rais J, Kyrs M (1979) Study of the possibility of using dicarbollides to extract cesium and strontium from waste radioactive solutions, Ustav Jad. Vyzk., [Rep.] (1979), (UJV 5069) pp 58Google Scholar
  52. Shannon RD (1976) Acta Cryst A32:751Google Scholar
  53. Shannon RD, Prewitt CT (1969) Acta Cryst B25:925Google Scholar
  54. Shannon RD, Prewitt CT (1970) Acta Cryst B26:1046Google Scholar
  55. Tachimori S, Nakamura H (1982) J Nucl Sci Technol 19(4):326CrossRefGoogle Scholar
  56. Tachimori S, Sato A, Nakamura H (1979) J Nucl Sci Technol 16(6):434CrossRefGoogle Scholar
  57. Vitorge P (1984) Lanthanides and trivalent actinides complexation by tripyridyl, triazine, Applications to liquid-liquid extraction, CEA-R-5270Google Scholar
  58. Weaver B, Kappelmann FA (1964) Talspeak: a new method of separating Americium and Curium from lanthanides by extraction from an aqueous solution of aminopolyacetic acid complex with a monoacidic phosphate or phosphonate, ORNL-3559, Oak Ridge National Laboratory, Oak RidgeGoogle Scholar
  59. Weigl M, Geist AM, Gompper K, Kim JI (2001) Solv Extr Ion Exch 19(2):215CrossRefGoogle Scholar
  60. Yakovlev GN, Gorbenko-Germanov DS (1956) Coprecipitation of Americium (V) with double carbonates Uranium (VI) or Platinum (vi) with Potassium. In: Proceedings of the 1st United Nations international conference on peaceful uses of atomic energy, Vol 7, International Atomic Energy Agency, ViennaGoogle Scholar
  61. Zhu Y (1995) Radiochimica Acta 68:95Google Scholar
  62. Zhu Y, Song C, Xu J, Yang D, Lui B, Chen J (1989) Chinese J Nucl Sci Eng 9:141Google Scholar

Copyright information

© Springer Science+Business Media B.V. 2011

Authors and Affiliations

  • P. A. Baisden
    • 1
  • C. E. Atkins-Duffin
    • 1
  1. 1.Lawrence Livermore National LaboratoryLivermoreUSA

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