PROCESSING OF POWER REACTOR FUELS. Eighteenth Quarterly Progress Report, January 1 to April 1, 1962

Technical Report · Fri Jun 01 04:00:00 EDT 1962

OSTI ID:4772449

Clark, A.T. Jr. comp.

In a continuing stady of the anodic dissolution of simulated power reactor fuels using the liquid contact technique, Zircaloy-clad UO/sub 2/ fuel assemblies were successfully disintegrated in the semiworks electrolytic dissolver. The ZrO/sub 2/ sludge that formed was difficult to keep suspended during tranafer to waste storage. In laboratory studies, an optimum voltage was found for disirtegrating zirconium, and high uranium losses were detected in the ThO/sub 2/ sludge formed in the anodic disintegration of Th-U alloy. Work was initiated on the problems of diasolving sodium-bonded fuels. The rate of corrosion of stainless steel vessels by boiling nitric acid contnining dissolved stainless steel was reduced significantly when carbon black or sulfur was present. The reducing agents converted corrosive Cr/sup +6/ to noncorrosive Cr/sup +3/ but did not reduce the corrosion caused by high concentrations of iron and nitrate. (auth)

• Research Organization: Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.
• NSA Number: NSA-17-004295
• OSTI ID: 4772449
• Report Number(s): DP-740
• Country of Publication: United States
• Language: English

Related Subjects

ANODES
BOILING
CARBON
CHROMIUM
CORROSION PROTECTION
DECOMPOSITION
ELECTRIC POTENTIAL
ELECTROLYSIS
FUEL CANS
FUEL ELEMENTS
FUELS
IONS
IRON
LOSSES
NITRATES
NITRIC ACID
POWER PLANTS
PRODUCTION
REACTOR TECHNOLOGY
REACTORS
REDUCTION
REPROCESSING
SODIUM COMPOUNDS
SOLUBILITY
STAINLESS STEELS
STORAGE
SULFUR
SUSPENSIONS
THORIUM ALLOYS
THORIUM OXIDES
TRANSPORT
URANIUM
URANIUM ALLOYS
URANIUM DIOXIDE
VESSELS
WASTE SOLUTIONS
ZIRCALOY
ZIRCONIUM
ZIRCONIUM OXIDES