SEPARATION OF Cs$sup 137$ FROM HIGH-ACTIVITY RADIOACTIVE WASTE

Journal Article · Tue Jan 01 00:00:00 EST 1963 · Bedrijf en Tech.

OSTI ID:4645717

A process was developed on a laboratory scale to separate Cs/sup 137/ from waste fuels of atomic reactors. The recovery of this powerful and industrially important gamma emitter of 30 years half life is said to be so simple as to make it possible on an industrial scale. It is based on the preferential absorption of Cs by ammonium phosphor-molybdate from the nitric acid solution of the waste material and the subsequent extraction of Cs from its absorber. This method is more practical than other processes which are based upon precipitation and recrystallization of cesium salts. It was successfully tested on waste solutions of very different compositions. (OID)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-17-038581
• OSTI ID: 4645717
• Journal Information: Bedrijf en Tech., Vol. Vol: 18; Other Information: Orig. Receipt Date: 31-DEC-63
• Country of Publication: Country unknown/Code not available
• Language: Dutch

Related Subjects

WASTE DISPOSAL AND PROCESSING
ADSORPTION
AMMONIUM COMPOUNDS
CESIUM 137
EFFICIENCY
GAMMA SOURCES
HALF-LIFE
ISOTOPE SEPARATION
LEACHING
MOLYBDENUM OXIDES
NITRIC ACID
PHOSPHORUS COMPOUNDS
REPROCESSING
SOLUTIONS
WASTE PROCESSING
WASTE SOLUTIONS