Advanced aqueous reprocessing in P&T strategies: Process demonstrations on genuine fuels and targets

Verfasser / Beitragende:
[Birgit Christiansen, C. Apostolidis, R. Carlos, O. Courson, J.-P. Glatz, R. Malmbeck, G. Pagliosa, K. Römer, D. Serrano-Purroy]
Ort, Verlag, Jahr:
2004
Enthalten in:
Radiochimica Acta/International journal for chemical aspects of nuclear science and technology, 92/8/2004(2004-08-01), 475-480
Format:
Artikel (online)
ID: 378930923
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024 7 0 |a 10.1524/ract.92.8.475.39283  |2 doi 
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245 0 0 |a Advanced aqueous reprocessing in P&T strategies: Process demonstrations on genuine fuels and targets  |h [Elektronische Daten]  |c [Birgit Christiansen, C. Apostolidis, R. Carlos, O. Courson, J.-P. Glatz, R. Malmbeck, G. Pagliosa, K. Römer, D. Serrano-Purroy] 
520 3 |a In the present work the performance of several processes used for advanced reprocessing of commercial LWR fuels as well as transmutation targets is compared. As a first step uranium and plutonium were recovered by PUREX type reprocessing. The raffinate, containing fission products including lanthanides and the minor actinides (MA) was used as feed for the second step in which minor actinides and lanthanides were separated from the bulk of the fission products. The five different processes tested use CMPO, DIDPA, TRPO, Diamide and CYANEX 923 as extractants. In the third step MA are separated from lanthanides. Here three processes were tested, i.e. using CYANEX 301, the synergistic mixture of di-chloro substituted CYANEX 301 and TOPO, and BTP solvents. Column-, batch- and continuous counter-current extraction techniques were used for the tests. The different processes will be described and discussed in terms of performances and efficiencies for Am and Cm separation. Efficient separation of MA from different genuine fuel solutions could be demonstrated and thereby also the possibility of closing a future transmutation fuel cycle. The combination of Diamide and BTP seems to be the best, among extractants tested, to achieve an efficient MA recovery from spent fuel. 
540 |a © 2004 Oldenbourg Wissenschaftsverlag GmbH 
690 7 |a Laboratory techniques, experiments  |2 nationallicence 
690 7 |a Analytical chemistry  |2 nationallicence 
690 7 |a Inorganic chemistry  |2 nationallicence 
700 1 |a Christiansen  |D Birgit  |4 aut 
700 1 |a Apostolidis  |D C.  |4 aut 
700 1 |a Carlos  |D R.  |4 aut 
700 1 |a Courson  |D O.  |4 aut 
700 1 |a Glatz  |D J.-P  |4 aut 
700 1 |a Malmbeck  |D R.  |4 aut 
700 1 |a Pagliosa  |D G.  |4 aut 
700 1 |a Römer  |D K.  |4 aut 
700 1 |a Serrano-Purroy  |D D.  |4 aut 
773 0 |t Radiochimica Acta/International journal for chemical aspects of nuclear science and technology  |d Oldenbourg Wissenschaftsverlag GmbH  |g 92/8/2004(2004-08-01), 475-480  |x 0033-8230  |q 92:8/2004<475  |1 2004  |2 92  |o ract 
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950 |B NATIONALLICENCE  |P 700  |E 1-  |a Courson  |D O.  |4 aut 
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950 |B NATIONALLICENCE  |P 700  |E 1-  |a Serrano-Purroy  |D D.  |4 aut 
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