Investigation of a hydrazine-free, electrochemical reduction of Pu(IV) in the Purex process
In the Purex process for reprocessing spent fuel elements, separation of uranium and plutonium is attained through a valency adjustment of Pu(III). This report describes the use of electrochemical methods in the absence of hydrazine for the adjustment of Pu(III), in place of nitrous oxide itself (or...
| Main Authors: | , , , |
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| Language: | unknown |
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2017
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| Subjects: | |
| Online Access: | http://www.osti.gov/servlets/purl/7777272 https://www.osti.gov/biblio/7777272 https://doi.org/10.2172/7777272 |
| Summary: | In the Purex process for reprocessing spent fuel elements, separation of uranium and plutonium is attained through a valency adjustment of Pu(III). This report describes the use of electrochemical methods in the absence of hydrazine for the adjustment of Pu(III), in place of nitrous oxide itself (or nitric oxide) as a reducing agent. This was tried at low acid concentrations in which nitrous acid no longer functions oxidatively. The following factors and effects were investigated: nitric acid concentration, current density, temperature, uranium content, surface area of electrodes, and the effect of very low hydrazine concentrations. In addition, the reoxidation properties of completely reduced Pu(III)-containing solutions were investigated. Results of laboratory experiments on purely aqueous systems were compared with those from TBP/dodecane/HNO/sub 3/ systems in a pulse column. Information gained from laboratory experiments on U/Pu separation in the absence of hydrazine was confirmed in pulse-column experiments. |
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