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

Studies of the Synthetic Inorganic Ion Exchanger. III. The Separation of the Fission Product by Means of a Stannic Phosphate Cation Exchanger

Journal Article · · Bulletin of the Chemical Society of Japan
DOI:https://doi.org/10.1246/bcsj.36.1324· OSTI ID:4080845
The mutual separation of various nuclides contained in fission product was carried out with a stannic phosphate cation exchanger. Various concentrations of nitric acid and ammonium chloride solutions were used as eluants, and the separation was performed on hydrogen- and ammoniumform exchangers. The separations of Sr/sup 89/- Cs/sup 137/, Sr/sup 89/Ce/sup 144/, Cs/sup 137/-Ce/sup 144/ and Sr/sup 90/--Y/sup 90/ were easy and com plete except for that of Cs/sup 137/-Ce/sup 144/ on a hydrogen-form exchanger. Zr/sup 95/ and Nb/sup 95/ were almost completely adsorbed on the exchanger over a wide range of acidity and salt concentration; therefore, they were not eluted at all. As the behavior of Ru/sup 106/ is complex and its separation from other nuclides is impossible, it is necessary to separate the ruthenium from the fission product in advance by a method other than that of ion exchange. With reference to the results, the total analysis of the fission product on an ammonium-form exchanger was carried out. It is almost complete except for the contamination of rare earth in the cesium fraction.
Research Organization:
Tohoku Univ., Sendai
Sponsoring Organization:
USDOE
NSA Number:
NSA-18-013922
OSTI ID:
4080845
Journal Information:
Bulletin of the Chemical Society of Japan, Journal Name: Bulletin of the Chemical Society of Japan Journal Issue: 10 Vol. 36; ISSN 0009-2673
Country of Publication:
Country unknown/Code not available
Language:
English