Abstract

The Purex solvent extraction process will be used in the nuclear fuel recovery and recycling center to reprocess up to 2100MT/yr of spent light water reactor fuels. Modifications to the process will be made to improve fission product decontamination and to treat gaseous and liquid radioactive waste streams. These modifications will allow overall decontamination factors for most fission products from recovered uranium and plutonium of >1010. No liquid process wastes will be released, and releases of radioactive materials in gaseous effluents will be as low as reasonably achievable.

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