Electrometallurgical Techniques for DOE Spent Fuel Treatment Final Report (2000) / Chapter Skim
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Appendix B Meeting Summary, July 21-22, 1999
Appendix B Meeting Summary, July 21-22, 1999
Pages 85-102
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Ceramic Waste Product Consistency Testing T.P. O'Holleran 3:00 p.m.
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Blanket treatment reports include Process Description for Blanket Treatment Operations and Development of the Electrorefining Process for Blanket Fuel. Waste operation and qualification reports are divided into three groups: overall waste reports, ceramic waste reports, and metal waste reports.
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The casting furnace during the demonstration treated 40 driver batches, 6 blanket batches, and 7 metal waste batches. Typical cathode processor/casting batch quantities were as follows: (1)
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Additional components of the average production rate include the frequency and duration of low-current strips and the duration of the washing step. A number of parameters affect the average production rate.
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Changes in operation parameters in general have the same qualitative effect in hot cell and glove box tests. Hot cell ACM tests show a somewhat lower average production rate (g~/ACM)
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would be recovered from treatment by EMT of the remaining blanket fuel in the DOE sodium-bonded SNF inventory. Approximately 1.6 MT of uranium ends up in the waste forms (0.89 MT in the metal waste form and 0.67 MT in the ceramic waste form)
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spectroscopy has been used for HUP waste form samples in bulk and powder form. Electron microscopy has been used for 238Pu-bearing HUP ceramic waste form samples.
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K.M. Goff, ANL-E, spoke on ceramic waste demonstration processing results.
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Repository performance assessment needs require the characterization of matrix corrosion behavior and radionuclide release, and also require a mechanistic model with model parameters. Waste specification needs require the identification of phases containing radionuclides, and methodology must be provided to monitor product consistency.
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This equation allows direct comparison of the release of different elements from different materials and at different S/V ratios. The MCC-1 test was developed in the early 1980s to evaluate the relative chemical durabilities of simulated and radioactive monolithic waste forms at low S/V ratios.
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. The uranium/plutonium ratio does not affect the microstructure of the ceramic waste form.
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The goal of product consistency testing of the CWF is to ensure that the waste form production process is well controlled. A wellcontrolled process will create waste form products that meet ANL's waste acceptance product specifications and can be subsequently disposed in a geologic repository.
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Dennis D Keiser, ,Ir., ANL-E, spoke about metal waste product testing.
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The three MWF ingots were cast in the FCF that incorporate an amount of cladding hulls corresponding to two driver assemblies, with the third MWF ingot having been cast using blanket hulls. The characterization techniques employed for the metal waste form product were bulk chemistry, SEM, an immersion test, and the TCLP analysis.
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The 39- to 9-isotope comparisons with only ANL waste are used to verify that actinide inventory adjustments are satisfactory for the ANL waste forms. The 9-isotope total dose rate time history agrees well with the 39-isotope result.
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A further goal is to consult with the cognizant branches of DOE about the spent fuel treatment process under development at ANL and the waste forms that will be produced. Pertinent legislation on this topic includes Nuclear Regulatory Commission legislation 10CFR60.
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ASTM C1174 provided the basis for developing the test matrices for the CWF and the MWF. These test matrices are extensive and will provide the data necessary to develop a model for assessing the performance of the waste forms that result from the spent fuel treatment process.
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