The liquid–liquid extraction (LLE) process for
lanthanide–actinide
separation from the nuclear fuel cycle has several drawbacks such
as, the requirement of cooling for decay heat control, the handling
of large volumes of toxic volatile organic compounds (VOCs), and secondary
waste generation. Alternatively reprocessing without spent fuel cooling
is done by pyroprocessing, which uses high-temperature corrosive molten
salts and requires elevated temperature, and is an energy-intensive
process. In recent years, some of the shortcomings of both LLE and
pyroprocessing are overcome by the use of room temperature ionic liquids
(RTILs) as the solvents. In the present work, an attempt was made
to exploit the potential of the neoteric, less-corrosive, low-VOC
RTILs toward direct dissolution-based separations at ambient conditions.
The present paper involves the selective dissolution of Eu2O3 in an RTIL, i.e., C4mim·NTf2 containing 2-thenoyltrifluoroacetone (HTTA) within ca. 30 min at
ambient conditions; while the dissolution of AmO2 and UO2 were found to be very poor, making this an attractive method
for lanthanide–actinide separation, a key step in radioactive
waste management, i.e., an actinide partitioning and transmutation
strategy. The quantitative dissolution of Eu2O3 from simulated spent nuclear fuel with different Eu2O3 loading was also shown. Water plays a crucial role in deciding
the kinetics of dissolution and amount of the dissolved oxide. The
combination of X-ray absorption, fluorescence, and UV–vis spectroscopic
studies suggested the formation of the dehydrated anionic complex
Ln(TTA)4
– to play pivotal role in the
oxide dissolution process. The structure of the complex was analyzed
by density functional theory and extended X-ray absorption fine structure.
The mechanism of oxide dissolution was proposed and electrochemical
studies were performed to understand the possible recovery option
using electrodeposition of the dissolved Eu3+.