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Title: THE SEPARATION OF URANIUM FROM NaF-KF-UF$sub 4$ AND NaF-ZrF$sub 4$-UF$sub 4$ WITH BrF$sub 3$

Abstract

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 KFmore » fusion-BrF/sub 3/ treatment. (auth)« less

Authors:
Publication Date:
Research Org.:
North American Aviation, Inc., Downey, Calif.
OSTI Identifier:
4816597
Report Number(s):
NAA-SR-269
NSA Number:
NSA-16-008809
DOE Contract Number:  
AT-11-1-GEN-8
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; BROMINE FLUORIDES; LEAD FLUORIDES; LIQUIDS; MELTING; MIXING; POTASSIUM FLUORIDES; QUANTITY RATIO; RUBIDIUM FLUORIDES; SALTS; SEPARATION PROCESSES; SODIUM FLUORIDES; URANIUM; URANIUM FLUORIDES; ZIRCONIUM FLUORIDES

Citation Formats

Keneshea, Jr, F J. THE SEPARATION OF URANIUM FROM NaF-KF-UF$sub 4$ AND NaF-ZrF$sub 4$-UF$sub 4$ WITH BrF$sub 3$. United States: N. p., 1953. Web.
Keneshea, Jr, F J. THE SEPARATION OF URANIUM FROM NaF-KF-UF$sub 4$ AND NaF-ZrF$sub 4$-UF$sub 4$ WITH BrF$sub 3$. United States.
Keneshea, Jr, F J. Wed . "THE SEPARATION OF URANIUM FROM NaF-KF-UF$sub 4$ AND NaF-ZrF$sub 4$-UF$sub 4$ WITH BrF$sub 3$". United States.
@article{osti_4816597,
title = {THE SEPARATION OF URANIUM FROM NaF-KF-UF$sub 4$ AND NaF-ZrF$sub 4$-UF$sub 4$ WITH BrF$sub 3$},
author = {Keneshea, Jr, F J},
abstractNote = {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)},
doi = {},
url = {https://www.osti.gov/biblio/4816597}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1953},
month = {8}
}

Technical Report:
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