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Waste Forms
Pages 13-16

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From page 13...
... there will be sufficient information available on ion-exchange loading of zeolite or sodalite under radioactive operating conditions and at relevant radionuclide concentrations to provide a basis for a decision to proceed with using electrometallurgical technology to treat spent fuel. In particular, it is worrisome that "hot" column ion-exchange tests will not be part of the EBR-II demonstration and that no fully loaded samples of the expected final ceramic waste form will be produced or characterized.
From page 14...
... ANL should remain alert to issues regarding the scale-up of the manufacturing process for any of these waste forms, especially with regard to the conditions (time, temperature, mixing, etc.) required to achieve an adequate degree of uniformity of salt loading inside each of the crystalline host phases.
From page 15...
... Conceptual Modelfor Ceramic Waste Form Performance ANL has recognized the importance of developing a conceptual model to assess how its proposed ceramic waste form will behave under long-term conditions in a deep geologic repository. ANL's preliminary conceptual model for reaction of Me ceramic waste fond with repository groundwater and subsequent transport of released radionuclides is divided into three steps: Step I: contact of the ceramic waste form with water andlor water vapor; Step II: primary release of radionuclides from the ceramic waste form; and 6 Argonne National Laboratory, Nuclear Technology, EBR-II Spent Fuel Treatment Program Monthly Report, March 1997.
From page 16...
... Furthermore, water-glass reactions typically lead to increases in pH and alkaline conditions, which could increase the dissolution rate of zeolitic materials. ANL does not yet have enough QT data on its proposed ceramic waste forms to unambiguously distinguish which release mechanism (Step II)


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