THE SEPARATION OF URANIUM FROM NaF-KF-UF$sub 4$ AND NaF-ZrF$sub 4$-UF$sub 4$ WITH BrF$sub 3$
Technical Report
·
OSTI ID:4816597
The use of the BrF/sub 3/ process in the removal of uranium from the fluoride mixtures NaF-KF-UF/sub 4/ (47-26-27 mole per cent, respectively) and NaF- ZrF/sub 4/-UF/sub 4/ (50-46-4 mole per cent, respectively) was investigated. More than 99 per cent of the uranium in the NaF-KF-UF/sub 4/ mixture was removed by direct treatment with liquid BrF/sub 3/. Effective separation of the uranium from the NaF-ZrF/sub 4/-UF/sub 4/ mixture required a pretreatment of the salt. Fusion with KF followed by BrF/sub 3/ treatment removed 95 per cent of the uranium from this fuel material. Direct treatment of the NaFof the uranium. Fusion of the zirconium-bearing fuel material with metallic fluorides other than KF, namely, NaF, RbF, and PbF/sub 2/ also improved the separation of uranium upon subsequent treatment with BrF/sub 3/. The best fluoride for fuel pretreatment was found to be KF. The extent of uranium removal from NaF-ZrF/sub 4/-UF/sub 4/ as a function of the amount of KF used in prefusion showed that a maximum separation of 95 per cent was obtained with a mole ratio of KF/ZrF/sub 4/ = 1. The uranium removal from NaF-ZrF/sub 4/UF/sub 4/ was increased to 98.2 per cent by employing a 2 cycle KF fusion-BrF/sub 3/ treatment. (auth)
- Research Organization:
- North American Aviation, Inc., Downey, Calif.
- DOE Contract Number:
- AT(11-1)-GEN-8
- NSA Number:
- NSA-16-008809
- OSTI ID:
- 4816597
- Report Number(s):
- NAA-SR-269
- Country of Publication:
- United States
- Language:
- English
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