Improvements in the Purex process by electrolytic methods (in German)
From 24th IUPAC congress; Hamburg, Germany (2 Sep 1973). In the Purex process, the separation of plutonium from uranium is accomplished by means of the reduction of Pu(IV) to the practically unextractable Pu(III). In order to avoid the introduction of extraneous corrosive ions, such as Fe(II) or, in the case of Purich fuel, a considerable expansion of process solutions by adding U(IV) as the reduction agent, an in-situ electrolytic procedure has been developed with a cathodic reduction of plutonium. An electrolytic mixer-settler has been built whose constructional principles are explained. The results of some electrolytic countercurrent extraction experiments for the separation of Pu/U, as well as the backextraction of Pu are given. Furthermore, the construction of an electrolytic pulse column is described, and the results of material balance experiments for the different apparatus types are reported. The advantages of the electrolytic process are discussed. (GE)
- Research Organization:
- Kernforschungszentrum, Karlsruhe, Ger.
- NSA Number:
- NSA-29-007653
- OSTI ID:
- 4368481
- Country of Publication:
- Germany
- Language:
- German
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