A5016375934- Radioactive element chemistry and processing
- Extraction and Separation Processes
- Chemical Synthesis and Characterization
- Analytical chemistry methods development
- Electrochemical Analysis and Applications
- Analytical Chemistry and Sensors
- Ionic liquids properties and applications
- Nuclear Materials and Properties
- Lanthanide and Transition Metal Complexes
- Nuclear materials and radiation effects
- Metal Extraction and Bioleaching
- Membrane Separation and Gas Transport
- Molten salt chemistry and electrochemical processes
- Atomic and Subatomic Physics Research
- Crystallization and Solubility Studies
- Nuclear reactor physics and engineering
Bhabha Atomic Research Centre
2015-2024
Homi Bhabha National Institute
2022-2024
The dissolution of metal oxide in ionic liquid (IL) medium is an important and challenging issue for the development alternative solvent systems carrying out non-aqueous chemistry operations ions nuclear field where IL could be a potential to high-temperature molten salt processing ions. This review article emphasizes on developments oxides particularly that uranium few other including those lanathanides which have relevance spent fuel (SNF) reprocessing. ILs broadly divided basis different...
A cellulose triacetate (CTA)-based polymer inclusion membrane (PIM) containing a C-pivot tripodal diglycolamide (T-DGA) as the carrier extractant and 2-nitrophenyl octyl ether (NPOE) plasticizer shows potential for uptake of actinides from acidic feed solutions. The (Am3+, Pu4+, Th4+, UO22+) was studied at 1 M HNO3 with PIMs 25.6% T-DGA, 53.9% NPOE, 20.5% CTA. metal ion followed trend: Pu4+ > Am3+ Th4+ UO22+, which in synch trend reported previously N,N,N′,N′-tetrakis(2-ethylhexyl) (T2EHDGA)...
Dissolution of uranium oxide was carried out using a solution HD2EHP in C8mim·NTf2, which apparently facilitated by the situ generation water during complex formation reaction. The dissolved ionic liquid phase led to splitting latter into light and heavy where former contained predominantly UO2(HL2)2 (HL = HD2EHP), while as supported FTIR UV–Visible spectral analyses. complexation uranyl ion suggested take place equatorial plane two dimeric units H-bonded molecules took part complexation. An...
Two tripodal amides obtained from nitrilotriacetic acid with n-butyl and n-octyl alkyl chains (HBNTA(LI) HONTA(LII), respectively) were studied for the extraction of Th(IV) ions nitric medium. The effect diluent medium, i.e., n-dodecane alone a mixture 1-decanol, onto aggregate formation investigated using small angle neutron scattering (SANS) studies. In addition, influence ligand structure, acid, loading aggregation third-phase tendency was discussed.The LI/LII exist as monomers...
The liquid-liquid extraction (LLE) process for lanthanide-actinide separation from the nuclear fuel cycle has several drawbacks such as, requirement of cooling decay heat control, handling large volumes toxic volatile organic compounds (VOCs), and secondary waste generation. Alternatively reprocessing without spent is done by pyroprocessing, which uses high-temperature corrosive molten salts requires elevated temperature, an energy-intensive process. In recent years, some shortcomings both...
Abstract Separation of neptunium from a mixture actinides viz. uranium, and plutonium was evaluated using two monoamides, N , ,-dihexyl octanamide (DHOA) decanamide (DHDA). The extraction with these ligands followed the order: U(VI)>Np(IV)>>Pu(III). Poor Pu(III) both amides (DHOA DHDA) exploited for mutual separation U, Pu Np. At 3 M HNO DHDA better extractant all three metal ions while one order magnitude lower DHOA as compared to that seen DHDA. Consequently, factor U(VI)/Np(IV)...
Polymer inclusion membranes (PIMs) containing N,N,N′,N′-tetra(2-ethylhexyl) diglycolamide (T2EHDGA), a branched extractant as the carrier, cellulose triacetate (CTA) polymer matrix, and 2-nitrophenyloctyl ether (NPOE) plasticizer were evaluated for recovery of actinide ions such Am3+, Pu4+, UO22+, Th4+ from acidic feed solutions. The optimized PIM composition used in this study was 69% T2EHDGA, 17% NPOE, 14% CTA. Sorption isotherm experiments carried out using macro concentrations Eu carrier...
Solutions of two nitrilotriacetamide (NTA) ligands, viz., N,N,N',N',N",N"-hexa-n-butylnitrilotriacetamide (HBNTA) and N,N,N',N',N",N"-hexa-n-hexylnitrilotriacetamide (HHNTA) in 20% isodecanol–80% n-dodecane were employed for the extraction U(VI), Np(IV), Pu(IV), Am(III) from nitric acid feed solutions. Limitations ligand solubility third-phase formation when contacted with solutions led to choice diluent composition isodecanol 80% n-dodecane. The results solvent studies indicated poor metal...
The present work envisages a chelation driven, facile, selective, and rapid method for uranium(VI) separation from (U, Th) mixture using 1-hydroxy-2-pyridone (1,2-HOPO). Herein, U(VI) was selectively precipitated as the neutral [UO
Extraction of Np(IV), Pu(IV), U(VI), and Np(VI) was studied using N,N-di-2-ethylhexyl derivatives iso-butyramide (D2EHIBA) n-propanamide (D2EHPrA). D2EHIBA showed higher selectivity for U(VI) over Np(IV) Pu(IV). A flowsheet the separation from a mixture uranium, neptunium, plutonium in 3 M HNO3 developed exploiting tetravalent actinides followed by selective stripping di-n-hexyl-octanamide (DHOA) medium acetohydroxamic acid (AHA). The results indicated that >90% neptunium present could be...
Abstract The present investigation deals with the development of a polyvinyl chloride (PVC) based potentiometric sensor for Eu(III) containing N,N,N’,N’ ‐tetrapentyl diglycolamide (TPDGA) as ionophore, 2‐nitrophenyl octylether (NPOE) plasticizer and sodium tetraphenylborate (NaTPB) ionic additive. membrane 8.7 % TPDGA, 29.7 PVC, 59.0 NPOE, 2.5 NaTPB exhibited linear response behaviour from 1.5×10 −6 m to 1.1×10 −2 slope 23.4±0.3 mV/decade limit detection (LOD) 1.2×10 . showed fast times...
The extraction of Np(IV) and Pu(IV) was studied using a tripodal amide ligand (N,N,N′,N′,N″,N″-hexa-n-octyl nitrilotriacetamide termed as HONTA) in an ionic liquid (C4mim·NTf2) well molecular diluent mixture (95% n-dodecane +5% iso-decanol) from aqueous feed containing diluted nitric acid. efficiency higher than that Np(IV), while the RTIL-based solvent system extracted metal ions better diluent-based system. species were ascertained by slope analysis M(NO3)5·L(LH) M(NO3)4·L2 for liquid-...
Though uranium is usually present in its +6 oxidation state (as uranyl ion) aqueous solutions, conversion to states such as +4 or +5 a challenging task. Electrochemical reduction and axial oxo activation are the preferred methods get stable unusual of an medium. In previous studies, dicarboxylic acid has been used stabilize UO2+ alkaline solutions. work, diphosphonate ligand was chosen due higher complexing ability compared that carboxylate ligands. Neptunium complexation studies with...