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Title: Development and study on an electroreduction mixer-settler for separation of plutonium during reprocessing of nuclear fuels

Thesis/Dissertation ·
DOI:https://doi.org/10.2172/7777629· OSTI ID:7777629

The history of reprocessing nuclear fuels began in the United States in the mid 1940s with the production of plutonium by precipitation according to the well-known bismuth phosphate process. Following that, other extraction methods, particularly by aqueous means, were developed that finally resulted in the Purex process that is used today worldwide. The largest facility in service reprocessing light water reactor fuel is at La Hague in France. This method is based on an extraction by tributyl phosphate (TBP) from nitric solutions. By diluting the TBP with approximately 30% volume of kerosene (essential component n-dodecane), a sufficiently great density difference is reached between the organic and aqueous media to obtain good separation of the phases in the extractors. For this separation, mixer-settlers, pulsed columns or centrifugal extractors can be used. Our research treats the use of mixer-settlers. 61 refs., 34 figs., 13 tabs.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
7777629
Report Number(s):
ORNL/tr-88/25; ON: DE89001721; TRN: 88-035421
Resource Relation:
Other Information: Thesis (Ph.D.). Portions of this document are illegible in microfiche products; Related Information: TN: Translated from French Microfilm of thesis presented to the Grenoble National Polytechnical Institute September 1984, Country of intellectual origin: United States
Country of Publication:
Germany
Language:
English