TY - JOUR
T1 - Highly efficient and selective extraction of Pu(IV) using two alkyl-substituted amides of nitrilo triacetic acid from nitric acid solutions
AU - Karak, Ananda
AU - Mahanty, Bholanath
AU - Mohapatra, Prasanta K.
AU - J. M. Egberink, Richard
AU - Valsala, Thichur P.
AU - Sathe, Darshan B.
AU - Bhatt, Raj B.
AU - Huskens, Jurriaan
AU - Verboom, Willem
N1 - Funding Information:
AK, TPV and DBS wish to thank Mr. K.V. Ravi, Chief Executive, Nuclear Recycles Board for his constant encouragement, while BNM and PKM acknowledge Dr. P.K. Pujari, Director, Radiochemistry and Isotope Group, BARC for his keen interest. AK also thanks Dr. P.K. Verma for carrying out Karl-Fisher titrations.
Publisher Copyright:
© 2021 Elsevier B.V.
PY - 2021/12/15
Y1 - 2021/12/15
N2 - Liquid-liquid extraction of the actinide ions UO22+, Pu4+, Am3+ was carried out from nitric acid feed solutions using two tripodal amide extractants, viz., N,N,N’,N’,N”,N”-hexa-n-octylnitrilotriacetamide (HONTA) and N,N,N’,N’,N”,N”-hexa-n-dodecylnitrilotriacetamide (HDDNTA) in 10% isodecanol + 90% n-dodecane diluent. The metal ion extraction trend was: Pu(IV) ≫ U(VI) > Am(III) at 3 M HNO3, HONTA being a superior extractant than HDDNTA. Slope analysis indicated ML2 type species for both Pu(IV) and Am(III) at 3 M HNO3 and pH 2.0, respectively, whereas, only in case of HONTA, a ML type species was obtained with U(VI) at 3 M HNO3. Back extraction data suggested that a mixture of 0.5 M HNO3 + 0.5 M oxalic acid was efficient for quantitative stripping (∼90%) of Pu(IV), whereas 1 M Na2CO3 and 1 M α-HIBA gave satisfactory back extraction for U(VI) and Am(III), respectively. The ligand solutions showed reasonably good radiation stability up to an absorbed total gamma ray dose of 274 kGy. Distribution data were also obtained under U(VI) loading conditions for possible nuclear fuel cycle applications.
AB - Liquid-liquid extraction of the actinide ions UO22+, Pu4+, Am3+ was carried out from nitric acid feed solutions using two tripodal amide extractants, viz., N,N,N’,N’,N”,N”-hexa-n-octylnitrilotriacetamide (HONTA) and N,N,N’,N’,N”,N”-hexa-n-dodecylnitrilotriacetamide (HDDNTA) in 10% isodecanol + 90% n-dodecane diluent. The metal ion extraction trend was: Pu(IV) ≫ U(VI) > Am(III) at 3 M HNO3, HONTA being a superior extractant than HDDNTA. Slope analysis indicated ML2 type species for both Pu(IV) and Am(III) at 3 M HNO3 and pH 2.0, respectively, whereas, only in case of HONTA, a ML type species was obtained with U(VI) at 3 M HNO3. Back extraction data suggested that a mixture of 0.5 M HNO3 + 0.5 M oxalic acid was efficient for quantitative stripping (∼90%) of Pu(IV), whereas 1 M Na2CO3 and 1 M α-HIBA gave satisfactory back extraction for U(VI) and Am(III), respectively. The ligand solutions showed reasonably good radiation stability up to an absorbed total gamma ray dose of 274 kGy. Distribution data were also obtained under U(VI) loading conditions for possible nuclear fuel cycle applications.
KW - Extraction
KW - Plutonium
KW - Tripodal amides
KW - Uranium
KW - 22/2 OA procedure
UR - http://www.scopus.com/inward/record.url?scp=85116325211&partnerID=8YFLogxK
U2 - 10.1016/j.seppur.2021.119584
DO - 10.1016/j.seppur.2021.119584
M3 - Article
AN - SCOPUS:85116325211
SN - 1383-5866
VL - 279
JO - Separation and purification technology
JF - Separation and purification technology
M1 - 119584
ER -