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Experiences of the hot reprocessing campaign of irradiated MTR fuel elements with an amine flowsheet at the Eurex plant Saluggia, Italy

Technical Report ·
OSTI ID:4938916
The results obtained during 1971 with the campaign for reprocessing highly enriched uranium, using tertiary aliphatic amines (TCA) diluted in Solvesso 100 as extractant, are reported. Flowsheet performances for U recovery, U/Pu (and Np) separation, and fission product decontamination are emphasized. A special final U purification was set up with an aliphatic hydroxamic acid highly soluble in organic diluent (HX). Pu(IV) and Np(IV) were selectively extracted to meet the transuranium alpha activity specifications for the final U product. The accountability system and procedures are described as adopted for the Eurex plant. A detailed analysis is made of the inventory at the end of this reprocessing campaign. (auth)
Research Organization:
Comitato Nazionale per l'Energia Nucleare, Rome (Italy)
Sponsoring Organization:
Sponsor not identified
NSA Number:
NSA-29-026771
OSTI ID:
4938916
Report Number(s):
RT/CHI--(73)10
Country of Publication:
Italy
Language:
English