Electrometallurgical Techniques for DOE Spent Fuel Treatment An Assessment of Waste Form Development and Characterization (1999) / Chapter Skim
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Executive Summary
Executive Summary
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4 National Research Council, Electrometallurgical Techniques for DOE Spent Fuel Treatment: Status Report on Argonne National Laboratory's R&D Activity as of Fall 1998, National Academy Press, Washington, D.C., 1999.
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R&D and evaluation led to the selection of glass-bonded socialite as the reference CWF. The committee in this report assesses waste qualification activities related to the MWF and CWF produced by this process and provides an evaluation of the technical consistency and comprehensiveness of the EMT activities that support ultimate acceptance of EMT waste fonns by DOE's Of lice of Civilian Radioactive Waste Management (RW)
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Metal Waste Forms The electrometallurg~cal treatment of spent EBR-~} reactor filet involves a set of Operations designed to disassemble driver and blanket filet pins, to refine and recover the uranium metal contained therein, and to segregate the radioactive waste components. For the entire EBR-~} spent fuel inventory, the base metal waste stream composition is stainless steel containing approx~nately 15 weight °/0 zirconium, labeled SS-lSZr by ANT personnel.9 Thus, MWF testing at Argonne National Laboratory-West (ANL-W)
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Finding: ANE's tests of several months' duration indicate that the CWF dissolves at a rate equal to or less than that of the reference DHEW borosilicate glass. Conclusion: If dissolution remains the dominant release mechanism under actual I Presentation to the committee by William Ebert, National Academies Beckman Center, Irvine, CA, January 28, 1999.
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The EMT Program's waste-form qualification program is based on adaptation of models and test protocols developed for DHEW borosilicate glass. Recommendation: The EMT Program should continue to evaluate and demonstrate that test protocols and conceptual models developed for monolithic single-phase borosilicate glass can adequately represent the behavior of the nonhomogeneous mul~ciphase EMT CWF.
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ADDITIONAL CONSIDERATIONS RELATED TO THE DEMONSTRATION PROJECT Disposition of the Uranium Product Stream Produced by the EMT Process The EMT Program staff has discussed applicable product purity levels with the staff of the Oak Ridge National Laboratory's Y-12 Plant for Y-12 acceptance of the uranium metal. If DOE decides that a commercial disposition option is desirable, some additional purification must be sought.
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