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U.S. Department of Energy
Office of Scientific and Technical Information

SOLVENT-EXTRACTION OF U$sup 233$ FROM NEUTRON-IRRADIATED THORIUM

Patent ·
OSTI ID:4168965

A solvent extraction process is described for separating U/sup 233/ from neutron-irradiated Th. A HNO/sub 3/ solution of the This made and contacted with methylisobutyl ketone. For separation from Pu an acidity adjustment and salting- out agent are used. (T.R.H.)

Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-14-014830
OSTI ID:
4168965
Report Number(s):
GB 833981
Country of Publication:
United Kingdom
Language:
English

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