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Partitioning and Transmutation of Long-Lived Fission Products

John A. Rawlins, D.W. Wootan, Richard A. Karnesky, F.M. Mann, W.W. Schulz

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Abstract

Concepts are summarized for partitioning of the long-lived fission products technetium-99 and iodine-129 from spent fuel and for transmutation of these fission products to stable isotopes. One small sample irradiation experiment in the Fast Flux Test Facility provides some confidence in calculated transmutation rates for both technetium-99 and iodine-129. The partitioning scheme assumes the existence of an aqueous reprocessing plant using the Plutonium/Uranium Extraction process. Numerous demonstration experiments would be in order to validate the concepts described. The toughest technical issue is probably development of suitable iodine transmutation targets. Finally, the authors conclude that an overall nuclear system assessment is warranted to determine the concepts most worthy of development.

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What this paper is about

Concepts are summarized for partitioning of the long-lived fission products technetium-99 and iodine-129 from spent fuel and for transmutation of these fission products to stable isotopes. One small sample irradiation experiment in the Fast Flux Test Facility provides some confidence in calculated transmutation rates for both technetium-99 and iodine-129. The partitioning scheme assumes the existence of an aqueous reprocessing plant using the Plutonium/Uranium Extraction process. Numerous demonstration experiments would be in order to validate the concepts described. The toughest technical issue is probably development of suitable iodine transmutation targets. Finally, the authors conclude that an overall nuclear system assessment is warranted to determine the concepts most worthy of development.

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Available abstract

Concepts are summarized for partitioning of the long-lived fission products technetium-99 and iodine-129 from spent fuel and for transmutation of these fission products to stable isotopes. One small sample irradiation experiment in the Fast Flux Test Facility provides some confidence in calculated transmutation rates for both technetium-99 and iodine-129. The partitioning scheme assumes the existence of an aqueous reprocessing plant using the Plutonium/Uranium Extraction process. Numerous demonstration experiments would be in order to validate the concepts described. The toughest technical issue is probably development of suitable iodine transmutation targets. Finally, the authors conclude that an overall nuclear system assessment is warranted to determine the concepts most worthy of development.

Key concepts: Nuclear transmutation, Fission products, Long-lived fission product, Radioactive waste, Nuclear fission product, Radiochemistry, Spent nuclear fuel, Fission

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