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@ARTICLE{Verlinden:907397,
author = {Verlinden, Bart and Van Hecke, Karen and Wilden, Andreas
and Hupert, Michelle and Santiago-Schübel, Beatrix and
Egberink, Richard J. M. and Verboom, Willem and Kowalski,
Piotr M. and Modolo, Giuseppe and Verwerft, Marc and
Binnemans, Koen and Cardinaels, Thomas},
title = {{G}amma radiolytic stability of the novel modified
diglycolamide 2,2′-oxybis( {N} , {N} -didecylpropanamide)
(m{TDDGA}) for grouped actinide extraction},
journal = {RSC Advances},
volume = {12},
number = {20},
issn = {2046-2069},
address = {London},
publisher = {RSC Publishing},
reportid = {FZJ-2022-02008},
pages = {12416 - 12426},
year = {2022},
abstract = {Reprocessing of spent nuclear fuel aims at improving
resource efficiency and reducing its radiotoxicity andheat
production in the long term. The necessary separation of
certain metal ions from the spent fuelsolutions can be
achieved using different solvent extraction processes. For
the scenario of the EUROGANEXprocess, the use of the new,
modified diglycolamide
2,20-oxybis(N,N-didecylpropanamide)(mTDDGA) was recently
proposed to simplify the current solvent composition and
reduce extraction offission products. Before further
developing the process based on this new ligand, its
stability underionizing radiation conditions needs to be
studied. For this reason, gamma irradiation experiments
wereconducted followed by analyses with high performance
liquid chromatography coupled to a massspectrometer
(HPLC-MS). The determined degradation rate of mTDDGA was
found to be lower than thatof the reference molecule N,N,N0
,N0-tetra-n-octyl-diglycolamide (TODGA). Many identified
degradationcompounds of both molecules are analogues showing
the same bond breaking, although alsounreported
de-methylation, double/triple de-alkylation and n-dodecane
addition products were observed.},
cin = {IEK-6 / ZEA-3 / IEK-13},
ddc = {540},
cid = {I:(DE-Juel1)IEK-6-20101013 / I:(DE-Juel1)ZEA-3-20090406 /
I:(DE-Juel1)IEK-13-20190226},
pnm = {1412 - Predisposal (POF4-141) / GENIORS - GEN IV Integrated
Oxide fuels recycling strategies (755171) / Atomistic
modeling of radionuclide-bearing materials for safe
management of high level nuclear waste.
$(jara0037_20191101)$ / 1221 - Fundamentals and Materials
(POF4-122)},
pid = {G:(DE-HGF)POF4-1412 / G:(EU-Grant)755171 /
$G:(DE-Juel1)jara0037_20191101$ / G:(DE-HGF)POF4-1221},
typ = {PUB:(DE-HGF)16},
UT = {WOS:000786641400001},
doi = {10.1039/D1RA08761D},
url = {https://juser.fz-juelich.de/record/907397},
}