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U.S. Department of Energy
Office of Scientific and Technical Information

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