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Review of Key Decontamination and Dismantlement Technologies

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Part of the book series: NATO ASI Series ((ASDT,volume 8))

Abstract

Final technology selection in any decontamination and dismantling (D&D) program is dependent on the following prerequisites:

  • a thorough radiation survey of all work areas and piping and equipment internals and external surfaces;

  • a thorough assessment of the activated material inventory by radionuclide and the distribution of that inventory in equipment and structures;

  • a detailed definition of the end product goal of the D&D program; and

  • a comparative cost estimate of different approaches to achieve that goal.

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Reference Materials for Further Review

  1. United States Department of Energy, by Nuclear Energy Services, Inc. Automation Industries (November, 1980), Decommissioning Handbook, DOE/EV/10128-1, Oak Ridge, Tennessee, USA.

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  2. United States Department of Energy, Office of Environmental Restoration (March, 1994), Decommissioning Handbook, DOE/EM-0142P, Oak Ridge, Tennessee, USA.

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  3. Tokai Research Establishment, Japan Atomic Energy Research Institute, “Reactor Decommissioning Technology Development and Actual Dismantling of JPDR,” Nakagun, Ibaraki-Ken, JAPAN.

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  4. Yanagihara, S. (November 9, 1994), “Progress of the JPDR Decommissioning Program,” Department of Decommissioning and Waste Management, Japan Atomic Energy Research Institute, Nakagun, Ibaraki-Ken, JAPAN.

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  5. Electric Power Research Institute (August, 1989), “Sourcebook for Chemical Decontamination of Nuclear Power Plants,” EPRINP-6433, Special Report, Palo Alto, California, USA.

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  6. Katayama, Y. B., Holton, L. K., Buck, G. N., Hutchens, J. F., and Culverhouse, M. S., Pacific Northwest Laboratory (July, 1991), “Advanced Remote Decontamination Techniques Reduce Costs and Radiation Doses,” Nuclear Technology, Vol. 95, American Nuclear Society, La Grange Park, Illinois, USA.

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  7. Wille, H., “Recent Experience with In-Situ Decontamination for Decommissioning,” an abstract, Siemens-AG, KWU S733, Freyeslebenstrasse 1, D-91058 Erlangen, Contract No. F12D-0067.

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  8. Boing, L. E., Henley, D. R., Manion, W. J., and Gordon, J. W. (December, 1989), “An Evaluation of Alternative Rector Vessel Cutting Technologies for the Experimental Boiling Water Reactor at Argonne National Laboratory,” ANL - 89/31, Argonne National Laboratory, Argonne, Illinois, USA.

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  9. Blumberg, R., “Technology for Dismantling Large Radioactive Structural Components,” an abstract, Holifield National Laboratory, Oak Ridge, Tennessee, USA.

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  10. Massaut, V., “Learning from BR-3,” Nuclear Engineering International, Sutton, Surrey SM2 5AS, United Kingdom.

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© 1996 Kluwer Academic Publishers

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Manion, W.J. (1996). Review of Key Decontamination and Dismantlement Technologies. In: LeSage, L.G., Sarkisov, A.A. (eds) Nuclear Submarine Decommissioning and Related Problems. NATO ASI Series, vol 8. Springer, Dordrecht. https://doi.org/10.1007/978-94-009-1758-3_27

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  • DOI: https://doi.org/10.1007/978-94-009-1758-3_27

  • Publisher Name: Springer, Dordrecht

  • Print ISBN: 978-94-010-7286-1

  • Online ISBN: 978-94-009-1758-3

  • eBook Packages: Springer Book Archive

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