Feasibility of neutron coincidence counting for spent TRISO fuel
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Three different solution-based approaches were taken to make sodalite minerals as a host for a mixed salt simulating the waste generated during the electrochemical separations process of nuclear fuel reprocessing that contains alkali, alkaline earth, and lanthanide chlorides plus trace iodine and actinides. All of the approaches included an aqueous solution of mixed chlorides (simulated waste) but the other reactants varied: (1) Al(OH)3 + NaOH + CS, (2) NaAlO2 + CS, and (3) Al2Si2O7 + NaOH, (CS = colloidal silica). The products were dried, ground, pressed into pellets, fired (650–950 °C), and characterized. Both 5 and 10 mass% of a Si-Na-B glass binder were introduced at different stages in the process. Route (2) proved the most successful at producing high sodalite fractions (up to 100%) with minimal glass binder additions and showed high consolidation potential (up to 91.4% of theoretical density). Detailed comparisons are provided of the results.
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