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The feasibility of transmutation strongly depends on an effective process. If the radiotoxic elements are supposed to be transmuted, the losses of the relevant elements in the various process schemes have to be be minimised. Thus a compromise has to be made between extraction and back-extraction capabilities of the extractant.

For the separation of long-lived radiotoxic elements from genuine high level liquid waste (HLLW) originated from LWR reactor fuel all 4 extractants tested (eg trialkyl (C6-C8) phosphine oxide (TRPO), n-octyl (phenyl)-N,N-diisobutyl carbamoylmethylphosphine oxide (CMPO), diisodecyl phosphoric acid (DIDPA) and dimethyldibutyltetradecylmenthylendiamide (DMDBTDMDA)) showed to be very efficient. Main differences were found in the back-extraction section of continuous counter-current extraction tests, carried out in a centrifugal extractor battery. .

Additional information

Authors: GLATZ J-P, JRC Karlsruhe (DE);NICOLL A, JRC Karlsruhe (DE);PAGLIOSA G, JRC Karlsruhe (DE);RÖMER K, JRC Karlsruhe (DE);SÄTMARK B, JRC Karlsruhe (DE);KOCH L, JRC Karlsruhe (DE)
Bibliographic Reference: Paper presented: OECD Workshop on Long Lived Radionuclide Chemistry in Nuclear Waste Treatment, Villeneuve-les-Avignon (FR), June 19-20, 1997
Availability: Available from (1) as paper EN 40590 ORA
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