Partitioning and transmutation of long-lived fission products
- Westinghouse Hanford Co., Richland, WA (United States)
- Schulz (W.W.), Wilmington, DE (United States)
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.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 10124424
- Report Number(s):
- WHC-SA--1444; CONF-920430--63; ON: DE92008385
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
052001
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALPHA-BEARING WASTES
FISSION PRODUCTS
FUEL REPROCESSING PLANTS
HIGH-LEVEL RADIOACTIVE WASTES
IODINE 129
PARTITION
RADIOISOTOPES
SEPARATION PROCESSES
SPENT FUELS
SPENT FUELS REPROCESSING
TECHNETIUM 99
TRANSMUTATION
WASTE PROCESSING