Recovery of transplutonium elements from fuel reprocessing high-level waste solutions
Technical Report
·
OSTI ID:4562409
A process for the recovery of americium and curium values from Purex-type high-level waste solutions is under development at Karlsruhe. The high-level waste is denitrated and the resulting fission product precipitate sent to HLW-solidification. The actinide/lanthanide fraction which has been kept in solution is separated by a HDEHP solvent extraction cycle. The lanthanides sent to waste solidification, while the Am/Cm is further purified by cation exchange. Results of 'cold' flowsheet tests are reported. (auth) 12 figs.; 2 tabs.; 11 refs.
- Research Organization:
- Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Heisse Chemie; Kernforschungszentrum Karlsruhe (F.R. Germany). Abt. Dekontaminationsbetriebe
- NSA Number:
- NSA-27-022307
- OSTI ID:
- 4562409
- Report Number(s):
- KFK--1651; CONF-721107--5
- Country of Publication:
- Germany
- Language:
- English
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ION EXCHANGE
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PUREX PROCESS
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SEPARATION PROCESSES
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