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Abstract
An investigation was performed of a flibe blanket to burn actinides extracted from the fission reactor spent fuel. It considered solubility of actinide fluoride in flibe, lithium-6 enrichment, and criticality concerns. Detailed burn-up calculations for a flibe medium containing 0.5 molar percent of actinide isotopes were completed. Performance parameters such as k-eff, tritium breeding ratio, and blanket energy multiplication during burn-up were obtained to assess the characteristics of a flibe based transmutation system. Technical issues associated with use of flibe for burning the transuranic actinides were identified.