Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Separation chemistry

Technical Report ·
OSTI ID:4143200
A method of preparing nitric acid solutions of iridium by fusion of the iridium in a KOH/KNO$sub 3$ mixture followed by dissolution of the fused iridium in nitric acid is described. The method may be adaptable to the separation of plutonium from iridium and suitable for decontaminating massive iridium. Process analytical data on 30 batches of Cotter Concentrate (approximately three drums) showed recovery of about 70 g of thorium 230 with 90 percent recovery efficiency. The behavior of the bone char/water system at pH 10 is being examined, and it has been found that bone char imposes low potentials on water at about pH 10. The behavior of hexavalent plutonium with bone char at pH 10 was also examined. The removal of uranium from waste streams by contact with bone char was studied along with the mechanism which involves the reduction of uranium in solution to ultra low levels. Experimental studies were initiated wherein an adsorption isotherm, involving the $sup 234$U bone char system, was measured. A total of 20.73 mg of $sup 229$Th has been separated from aged $sup 233$U. In addition, 1.63 mg $sup 229$Th was separated from $sup 233$U that has been previously processed. Processing of solutions A13-B and A13-B2 was completed through the three separation stages. The uranium was precipitated from the final solutions and calcined to the oxide. The total oxide weight of this product, designated A13-2, is 22.285 g. When all analyses have been completed and the weight of $sup 234$U calculated, the product will be shipped. (auth)
Research Organization:
Mound Lab., Miamisburg, Ohio (USA)
NSA Number:
NSA-33-008861
OSTI ID:
4143200
Report Number(s):
MLM--2241
Country of Publication:
United States
Language:
English