SEPARATION OF TECHNETIUM FROM MIXED FISSION PRODUCTS BY SOLVENT EXTRACTION WITH TRIBUTYL PHOSPHATE

Technical Report · Thu Dec 20 04:00:00 EST 1962

OSTI ID:4645071

Campbell, M H

Pertechnetate was found to extract quantitatively in a 45% tributyl phosphate --1M sulfuric acid system. Distribution ratios were determined as functions of hydrogen ion molarity and tributyl phosphate concentration. Sodium fluoride, added to the extraction system and an aqueous scrub, provided the necessary zirconium-niobium decontamination. A cation exchange column was used just prior to mounting to provide decontamination from metallic ions such as uranium. The overall decontamination provided by this method was 2 x 10/sup 4/ for zirconium-niobium95 and 1 x 10/sup 4/ for ruthenium-103-108. The method can be completed in 45 minutes with a pertechnetate recovery of 92%, and a precision at the 95 per cent confidence level of plus or minus 1.6 per cent. (auth)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• DOE Contract Number: AT(45-1)-1350
• NSA Number: NSA-17-039101
• OSTI ID: 4645071
• Report Number(s): HW-75943
• Country of Publication: United States
• Language: English

Related Subjects

ACIDITY
BUTYL PHOSPHATES
CATIONS
CHEMISTRY
CONCENTRATION
DECONTAMINATION
DISTRIBUTION
EFFICIENCY
ERRORS
FISSION PRODUCTS
HYDROGEN COMPOUNDS
ION EXCHANGE
ION EXCHANGE MATERIALS
IONS
METALS
NIOBIUM
NIOBIUM COMPOUNDS
PERTECHNETATES
QUANTITATIVE ANALYSIS
QUANTITY RATIO
RADIOCHEMISTRY
RECOVERY
RUTHENIUM
RUTHENIUM COMPOUNDS
SEPARATION PROCESSES
SODIUM FLUORIDES
SOLVENT EXTRACTION
SULFURIC ACID
TBP
TECHNETIUM
TECHNETIUM COMPOUNDS
TECHNETIUM OXIDES
URANIUM
URANIUM COMPOUNDS
WATER
ZIRCONIUM
ZIRCONIUM COMPOUNDS