THE DEVELOPMENT OF A METHOD FOR THE PREPARATION OF LARGE AMOUNTS OF 234-TH PURIFIED 238-U OXIDE
High purity 238-U oxide in amounts up to 60g is required for capture cross-section measurements. The material needs to be purified for the 234-Th daughter of 238-U in order to reduce the natural gamma background. It has been shown that 60g of U-3O-8 can be purified by cation exchange and retransformed in U-3O-8 in about 20 h. When the target is ready for the use the 234-Th content is 2% of the saturation value.
Bibliographic Reference: 12TH WORLD CONFERENCE OF THE INTERNATIONAL NUCLEAR TARGET DEVELOPMENT SOCIETY, ANVERS (BELGIUM), SEPT. 25-28, 1984, PUBL. IN: NUCLEAR INSTRUMENTS AND METHODS IN PHYSICS RESEARCH, VOL. A236 (1985), PP. 493-496
Record Number: 1989123087100 / Last updated on: 1987-01-01
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