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Clean Option: An Alternative Strategy for Hanford Tank Waste Remediation; Detailed Description of First Example Flowsheet

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Chemical Pretreatment of Nuclear Waste for Disposal

Abstract

Disposal of high-level tank wastes at the Hanford Site is currently envisioned* to divide the waste between two principal waste forms: glass for the high-level waste (HLW) and grout for the low-level waste (LLW). Several approaches have been proposed to accomplish this division; these approaches lead to a range of volumes of both the HLW and LLW fractions and a range of long-term risks associated with the disposed LLW. These approaches do not include emphasis on the waste minimization issues that are involved in the “clean option” discussed in this paper.

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References

  • 10 CFR 61, 1988, U. S. Nuclear Regulatory Commission, Licensing Requirements for Land Disposal of Radioactive Waste, “U.S. Code of Federal Regulations.”

    Google Scholar 

  • Beard, S.J., and Caudill, H.L., 1964, “Technetium Recovery and Storage at B-Plant,” HW-83348, General Electric Co., Richland, Washington.

    Google Scholar 

  • Bibler, J.P., and Wallace, R.M., 1987, “Preparation and Properties of a Cesium Specific Resorcinol — Formaldehyde Ion Exchange Resin,” DPST-87-647, Savannah River Laboratory, Aiken, South Carolina.

    Google Scholar 

  • Bibler, N.E., Hoisington, J.E., and Holtzcheiter, E.W., 1981, “Technical Data Summary Decomposition of Oxalic Acid by the Manganese Catalyzed Nitric Acid Reaction,” DPSTD-80-36, Savannah River Laboratory, Aiken, South Carolina.

    Google Scholar 

  • Bond, W. D., 1990, The thorex process, in: “Science and Technology of Tributyl Phosphate,” Schulz, W.W., Burger, L.L., and Navratil, J.D., eds., Volume III, CRC Press, Inc., Boca Raton, Florida.

    Google Scholar 

  • Bray, L.A., Elovich, R.J., and Carson, K.J., 1990, “Cesium Recovery Using Savannah River Laboratory Resorcinol-Formaldehyde Ion Exchange Resin,” PNL-7273, Pacific Northwest Laboratory, Richland, Washington.

    Book  Google Scholar 

  • Bray, L.A., Lust, L.F., Moore, R.L., Roberts, F.P., Smith, F.M., Van Tuyl, H.H., and Wheelwright, E.J., 1964, “Recovery and Purification of Multikilocurie Quantities of Fission Product Strontium by Cation Exchange,” Chemical Engineering Progress Symposium Series 47, Volume 60, pp. 9–19.

    Google Scholar 

  • Buck, J.W., and Peffers, M.S., 1991, “Preliminary Recommendations on the Design of the Characterization Program for the Hanford Site Single-Shell Tanks-A System Analysis,” PNL-7573, Vol. 2, Pacific Northwest Laboratory, Richland, Washington.

    Book  Google Scholar 

  • Buckingham, J.S., et al., 1967, “Waste Management Technical Manual,” ISO-100 DEL, Isochem, Inc., Richland, Washington.

    Book  Google Scholar 

  • Campbell, D.O., and Lee, D.D., 1991, “Treatment Options and Flowsheets for ORNL Low-Level Liquid Waste Supernate,” ORNL/TM-11800, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

    Google Scholar 

  • Delegard, C.H., 1985, “Solubility of PuO2 x H2O in Alkaline Hanford High-Level Waste Solution,” RHO-RE-SA-75P, Rockwell Hanford Operations, Richland, Washington.

    Google Scholar 

  • Droppo, J.G., Jr., et al., 1991, “Single-Shell Tank Constituent Rankings for Use in Preparing Waste Characterization Plans,” PNL-7572, Pacific Northwest Laboratory, Richland, Washington.

    Google Scholar 

  • Faubel, W., and Ali, S.A., 1986, Separation of cesium from acid ILW-PUREX solutions by sorption on inorganic ion exchangers, Radiochimica Acta 40: 49–56.

    CAS  Google Scholar 

  • General Electric, 1964, “Quarterly Progress Report — A Study of Tungsten-Technetium Alloys, April 1, 1964 — July 1, 1964,” HW-83550, General Electric Co., Richland, Washington.

    Google Scholar 

  • Grygiel, M.L., Augustine, CA., Cahill, MA., Garfield, J.S., Johnson, M.E., Kupfer, M.J., Meyer, GA., and Roecker, J.H., 1991, “Tank Waste Disposal Program Redefinition,” WHC-EP-0475, Rev. 0, Westinghouse Hanford Company, Richland, Washington.

    Book  Google Scholar 

  • Horwitz, E.P., 1993, Combining extradant systems for the simultaneous extraction of transuranic elements and selected fission products, in: “Proceedings of the First Hanford Separation Science Workshop,” July 23-25, 1991, Richland, Washington, PNL-SA-21775, Pacific Northwest Laboratory, Richland, Washington.

    Google Scholar 

  • Horwitz, E.P., Dietz, M.L., and Fisher, D.E., 1991, SREX. A new process for the extraction and recovery of strontium from acidic nuclear waste streams, Solvent Extraction and Ion Exchange 9: 1–25.

    Article  CAS  Google Scholar 

  • Horwitz, E.P., Diamond, H., Gatrone, R.C., Nash, K.L., and Rickert, P.G., 1990, “TUCS: A New Class of Aqueous Complexing Agents for Use in Solvent Extraction Processes,” presented at the International Solvent Extraction Conference, ISEC-90, July 20, 1990, Kyoto, Japan.

    Google Scholar 

  • Horwitz, E.P., Kalina, D.G., Diamond, H., Vandegrift, G.F., and Schulz, W.W., 1985, The TRUEX process — a process for the extraction of the transuranic elements from nitric acid wastes utilizing modified PUREX solvent, Solvent Extraction and Ion Exchange 3: 75–109.

    Article  CAS  Google Scholar 

  • Jantzen, C.M., 1990, Formation of Zeolite During Caustic Dissolution of Fiberglass: Implications for Studies of the Kaolinite-to-Mullite Transformation, J. Am. Ceram. Soc. 73(12): 3708–3711.

    Article  CAS  Google Scholar 

  • Koch, G., 1969, “Recovery of By-Product Actinides from Power Reactor Fuels,” KFK-976, Gesellschaft fur Kernforschung, Karlsruhe, Germany.

    Google Scholar 

  • Kolarik, Z., 1991, “Separation of Actinides and Long-Lived Fission Products from High-Level Radioactive Waste (A Review),” KfK 4945, Kernforschungszentrum Karlsruhe, Karlsruhe, Germany.

    Google Scholar 

  • Lumetta, G J., and Swanson, J.L., 1993, “Pretreatment of Plutonium Finishing Plant (PFP) Sludge: Report for the Period October 1990-March 1992,” PNL-8601, Pacific Northwest Laboratory, Richland, Washington.

    Google Scholar 

  • Lumetta, G.J., Wagner, M.J., Colton, N.G., and Jones, E.O., 1993, “Underground Storage Tank Integrated Demonstration, Evaluation of Pretreatment Options for Hanford Tank Wastes,” PNL-8537, Pacific Northwest Laboratory, Richland, Washington.

    Book  Google Scholar 

  • Marsh, S.F., and Yarbro, S.J., 1988, “Comparative Evaluation of DHDECMP and CMPO as Extractants for Recovering Actinides from Nitric Acid Waste Streams,” LA-11191, Los Alamos National Laboratory, Los Alamos, New Mexico.

    Google Scholar 

  • Roberts, F.P., Smith, F.M., and Wheelwright, E.J., 1963, “Recovery of Technetium from Hanford Waste,” HW-SA-2851, General Electric Co., Richland, Washington.

    Google Scholar 

  • Schulz, W.W., 1980, “Removal of Radionuclides from Hanford Defense Waste Solutions,” RHO-SA-51, Rockwell Hanford Operations, Richland, Washington.

    Google Scholar 

  • Smith, H.D., Mackey, D.B., Pool, K.H., and Schwenk, E.B., 1992, Corrosion resistance of stainless steels and high Ni-Cr alloys to acid fluoride wastes, in: “Proceedings of the Third International Conference on High Level Radioactive Waste Management,” April 12-16, 1992, Las Vegas, Nevada.

    Google Scholar 

  • Straalsund, J.L., Swanson, J.L., Baker, E.G., Holmes, J.J., Jones, E.O., and Kuhn, W.L., 1992, “Clean Option: An Alternative Strategy for Hanford Tank Waste Remediation, Volume 1. Overview,” PNL-8388 Vol. 1, Pacific Northwest Laboratory, Richland, Washington.

    Google Scholar 

  • Thompson, G.H., Childs, E.L., Kochen, R.L., Schmunk, R.J., Smith, C.M., 1979, “Actinide Recovery from Combustible Waste: The Ce(IV)-HNO3 System Final Report,” RFP-2907, Rocky Flats Plant, Golden, Colorado.

    Google Scholar 

  • U.S. Department of Energy (DOE), 1987, “Final Environmental Impact Statement — Disposal of Hanford Defense High-Level, Transuranic, and Tank Wastes,” DOE/EIS-0113, Richland, Washington.

    Google Scholar 

  • Vialard, E., and Germain, M., 1986, “Technetium Behavior Control in the Purex Process,” ISEC ′86 International Solvent Extraction Conference Preprints, p. 1–137, DECHEMA, Frankfurt am Main, Germany.

    Google Scholar 

  • Wheelwright, E.J., Bray, L.A., Van Tuyl, H.H., and Fullam, H.T., 1974, “Flowsheet for Recovery of Curium from Power Reactor Fuel Reprocessing Waste,” BNWL-1831, Pacific Northwest Laboratory, Richland, Washington.

    Book  Google Scholar 

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© 1995 Springer Science+Business Media New York

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Swanson, J.L. (1995). Clean Option: An Alternative Strategy for Hanford Tank Waste Remediation; Detailed Description of First Example Flowsheet. In: Schulz, W.W., Horwitz, E.P. (eds) Chemical Pretreatment of Nuclear Waste for Disposal. Springer, Boston, MA. https://doi.org/10.1007/978-1-4615-2526-4_12

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  • DOI: https://doi.org/10.1007/978-1-4615-2526-4_12

  • Publisher Name: Springer, Boston, MA

  • Print ISBN: 978-1-4613-6076-6

  • Online ISBN: 978-1-4615-2526-4

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