The Melt-Dilute Disposition Option for ²³³U

Conference · Sun Jun 04 04:00:00 EDT 2000

OSTI ID:753551

Adams, Thad M. ^[1]; Peacock, Jr., Harold B. ^[1]; Sindelar, Robert L. ^[1]

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1. Savannah River Site (SRS), Aiken, SC (United States)

The Melt-Dilute treatment technology is being developed by the Savannah River Technology Center (SRTC) for treatment of aluminum-base spent nuclear fuel. The MD technology has applicability for treatment of ²³³U oxide stored in either aluminum or stainless steel cans at Oak Ridge. This technology not only reduces the risk for criticality but also reduces proliferation concerns by diluting the fissile material to less the 12 percent ²³³U and less than 20 percent ²³⁵U. The resulting alloy is then dry stored temporarily in road-ready canisters until ultimate disposal in a geologic repository.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC09-96SR18500
• OSTI ID: 753551
• Report Number(s): WSRC-MS--2000-00199
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
ALUMINIUM ALLOYS
CONTAINERS
CRITICALITY
DEPLETED URANIUM
DILUTION
FISSILE MATERIALS
MELTING
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
OXIDES
PROLIFERATION
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
SAVANNAH RIVER PLANT
SPENT FUELS
STAINLESS STEELS
URANIUM 233
URANIUM 235
WASTE FORMS