Engineering study: Fast Flux Test Facility fuel reprocessing (open access)

Engineering study: Fast Flux Test Facility fuel reprocessing

Several alternatives were studied for reprocessing FFTF fuels at Hanford. Alternative I would be to decontaminate and trim the fuel at T Plant and electrolytically dissolve the fuel at Purex. Alternative II would be to decontaminate and shear leach the fuels in a new facility near Purex. Alternative III would be to decontaminate and store fuel elements indefinitely at T Plant for subsequent offsite shipment. Alternative I, 8 to 10 M$ and 13 quarter-years; for Alternative II, 24 to 28 M$ and 20 quarter-years; for Alternative III, 3 to 4 M$ and 8 quarter-years. Unless there is considerable slippage in the FFTF shipping schedule, it would not be possible to build a new facility as described in Alternative II in time without building temporary storage facilities at T Plant, as described in Alternative III. (auth)
Date: January 7, 1974
Creator: Beary, M. M.; Raab, G. J.; Reynolds, W. R., Jr. & Yoder, R. A.
System: The UNT Digital Library
Capabilities and resources for tritium research and development (open access)

Capabilities and resources for tritium research and development

Information and flow diagrams are presented from a presentation on tritium research and development activities at the Mound Laboratory. Topics include metal-hydrogen systems, gas dynamics and cryogenic separations, materials research, and helium diffusion and tritium effluent control.
Date: February 7, 1974
Creator: unknown
System: The UNT Digital Library