THE TREATMENT OF IRRADIATED THORIUM (in French)
Journal Article
·
· Bull. Inform. Sci. Tech. (Paris)
OSTI ID:4735152
The in-pile irradiation of natural thorium yields a fissile material: U/ sup 233/. The treatment of irradiated thorium was the object of studies carried out on a small pilot-plant scale. The principle governing the various operations of the process used, the difficulties encountered, and the first results obtained are described. The U/sup 233/ loss was 2.5 x 10/sup -3/ and that of thorium was 8 x 10/sup -3/. The main difficulty was the decontamination of thorium and uranium of Pa/sup 233/. The final purification on ion-exchange resins makes this possible, however. (auth)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-17-018193
- OSTI ID:
- 4735152
- Journal Information:
- Bull. Inform. Sci. Tech. (Paris), Journal Name: Bull. Inform. Sci. Tech. (Paris) Vol. Vol: No. 66
- Country of Publication:
- Country unknown/Code not available
- Language:
- French
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