REPROCESSING OF POWER REACTOR FUELS. Quarterly Progress Report No. 12 for July 1, 1960 to October 1, 1960

Technical Report · Sun Jan 01 04:00:00 EST 1961

OSTI ID:4117927

Occhipinti, E.S. comp.

Unirradiated elements made of graphite- 14% uranium, UO/sub 2/ clad with stainless steel, and UO/sub 2/ clad with Zircaloy-2 were disintegrated electrolytically in boiling 10M nitric acid. The sludge deposited at the bottom of the dissolver contained less than 0.1% of the total uranium for each test; the remainder of the uranium went into solution. Excessive loss of uranium (20 to 60% of the total uranium) to the sludge formed when unirradiated zirconium-low uranium alloy disintegrated electrolytically in 10M nitric acid was not effectively reduced by varying current densities from 0.03 to 2.5 amp/cm/sup 2/, with alternating current, direct current, or interrupted direct current. The sludge formed when unirradiated zirconium-low uranium alloy disintegrated electrolytically in potassium iodide contained 9 to 15% of the total uranium. (auth)

• Research Organization: Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.
• NSA Number: NSA-15-007405
• OSTI ID: 4117927
• Report Number(s): DP-546
• Country of Publication: United States
• Language: English

Related Subjects

ALTERNATING CURRENT
BOILING
CHEMISTRY
CURRENTS
DENSITY
ELECTRICITY
ELECTROLYSIS
FUELS
GRAPHITE
NITRIC ACID
POTASSIUM IODIDES
POWER
REACTORS
REPROCESSING
SLURRIES
STAINLESS STEELS
URANIUM
URANIUM ALLOYS
URANIUM DIOXIDE
ZIRCALOY
ZIRCONIUM