Published August 1994 | Version v1
Journal article

Separation and purification of 234Th from aged uranium salt

Creators

  • 1. Academia Sinica, Beijing, BJ (China). Inst. of Atomic Energy

Description

There are two flowsheets for the separation and purification of 234Th from aged uranium salt one is TBP extraction, anion exchange and TTA extraction; the other is Cation and anion exchange, TTA extraction. The total recovery efficiency of 234Th is about 90%. The γ-spectrum of the end-product contains only two typical peaks of 234Th (63 and 92 keV). Pure 234Th is prepared

Additional details

Publishing Information

Journal Title
Nuclear Science and Techniques
Journal Volume
5
Journal Issue
3
Journal Page Range
p. 181-183.
ISSN
1001-8042
CODEN
NSETEC