First Hydrolysis Constant of Lutetium (III) by Solvent Extraction

The solvent extraction method involving diglycolic acid (dicarboxy methyl ether) as a competitive ligand to lutetium and N-tris[hydroxymethyl]methyl-2-aminoethanesulfonic acid (TES) as a buffer was used to study the hydrolysis of lutetium in 1 mol⋅dm⁻³ NaCl ionic strength at 303 K. Acid dissociation constants of H₂DG and TES were determined and the possible formation of lutetium–TES compounds was investigated. It was found that lutetium does not form compounds with TES under the experimental conditions. The solvent extraction method using ¹⁷⁷Lu as a tracer was applied and the first hydrolysis constant of lutetium was determined by means of the relationship of the equilibrium constant of the complex Lu(DG)⁺ in the absence and in the presence of hydrolysis. The value obtained was log ₁₀ β _Lu,H=−7.9±0.3.     

Determination of Rare-Earth Elements in Sulfide Minerals by Inductively Coupled Plasma Mass Spectrometry with Ion-Exchange Preconcentration

A procedure was developed for determining ultratrace rare-earth elements in sulfide minerals by inductively coupled plasma mass spectrometry with ion-exchange preconcentration. The concentration factor was 200. The found concentrations of rare-earth elements were 6–30 times lower than those in chondrites. For lanthanum and praseodymium, RSD < 10%; for other rare-earth elements, RSD < 6%. The accuracy of the results was verified by the addition of known amounts of Eu, Tb, Tm, and Lu to a chalcopyrite sample at the stage of decomposition with HCl and HNO₃. The calculated yield of rare-earth elements was 94–96%. The detection limit was from 0.06 ng/g (6 × 10^–9%) for lutetium to 5 ng/g (5 × 10^–7%) for cerium. The procedure was used for the determination of rare-earth elements in chalcopyrites, pyrites, and sphalerites.     

Electrodeposition of Lu on W and Al electrodes: Electrochemical formation of Lu–Al alloys and oxoacidity reactions of Lu(III) in the eutectic LiCl–KCl

The electrodeposition of lutetium on inert electrodes and the formation of lutetium–aluminium alloys were investigated in the eutectic LiCl–KCl in the temperature range 673–823 K. On a tungsten electrode, the electroreduction of Lu(III) proceeds in a single step and electrocrystalization plays an important role. Experimental current–time transients are in good agreement with theoretical models based on either instantaneous or progressive nucleation with three dimensional growth of the nuclei, depending on the working temperature. The diffusion coefficient of Lu(III) was determined by chronopotentiometry by applying the Sand equation. The activation energy for diffusion was found to be 31.5 ± 1.3 kJ mol⁻¹. Al₃Lu and mixtures of Al₃Lu and Al₂Lu, characterized by XRD analysis and SEM, were obtained from the LiCl–KCl melt containing Lu(III) by potentiostatic electrolysis using an Al electrode. The activity of Lu and the standard Gibbs energies of formation for Al₃Lu were estimated from open-circuit chronopotentiometric measurements. The E–pO²⁻(potential–oxoacidity) diagram for Lu–O stable compounds in LiCl–KCl at 723 K has been constructed by combining theoretical and experimental data. In this way, the apparent standard potential for the Lu(III)/Lu system has been determined by potentiometry. Potentiometric titrations of Lu(III) solutions with oxide donors, using a yttria stabilized zirconia membrane electrode “YSZME” as a pO²⁻ indicator electrode, have shown the stability of LuOCl and Lu₂O₃ in the melt and their solubility products have been determined at 723 K.     

An Asymetric Lutetium(III) Microsensor Based on N‐(2‐Furylmethylene) Pyridine‐2,6‐Diamine for Determination of Lutetium(III) Ions

Abstract

In this work, for the first time, we introduce a highly selective and sensitive lutetium(III) micro‐sensor. N‐(2‐furylmethylene) pyridine‐2,6‐diamine (FPD) was used as a membrane‐active component to prepare a highly sensitive Lu(III)‐selective polymeric membrane microelectrode. Theoretical calculations for FPD, lutetium and some other metal ions were carried out and selectivity toward Lu(III) ions was confirmed. The best performance was achieved by a membrane composed of 32% PVC, 60% o‐nitrophenyloctyl ether, 4% potassium tetrakis (p‐chlorophenyl) borate (KTpClPB) and 4% FPD. The electrode exhibits a Nernstian response for Lu(III) ions over a particular concentration range (1.0×l0^?11?1.0×10^?6 mol l^?1) with a slope of 20.5±0.2 mV decade^?1. The detection limit is 3.0×10^?11 mol l^?1 while the sensor presents a response time of <10 s and a useful working pH range of 4.0–10.5. As a matter of fact, the proposed sensor discriminates relatively well for Lu(III) ions in compare to common alkali, alkaline earth, heavy metals and, specially, lanthanide ions. The sensor was successfully applied as an indicator electrode in a potentiometric titration of Lu(III) ions with EDTA. In addition, it was used for determination of lutetium in some soil samples where domestic devices were stored. The proposed sensor was evaluated for Lu(III) ions determination in some binary mixtures.     

Solubility and hydrolysis of lutetium at different [Lu<Superscript>3+</Superscript>]<Subscript>initial</Subscript>

Solubility product (Lu(OH)_3(s)⇆Lu³⁺+3OH⁻) and first hydrolysis (Lu³⁺+H₂O⇆Lu(OH)²⁺+H⁺) constants were determined for an initial lutetium concentration range from 3.72·10⁻⁵ mol·dm⁻³ to 2.09·10⁻³ mol·dm⁻³. Measurements were made in 2 mol·dm⁻³ NaClO₄ ionic strength, under CO₂-free conditions and temperature was controlled at 303 K. Solubility diagrams (pLu_aq vs. pC _H) were determined by means of a radiochemical method using ¹⁷⁷Lu. The pC _H for the beginning of precipitation and solubility product constant were determined from these diagrams and both the first hydrolysis and solubility product constants were calculated by fitting the diagrams to the solubility equation. The pC _H values of precipitation increases inversely to [Lu³⁺]_initial and the values for the first hydrolysis and solubility product constants were log₁₀ β* _Lu,H = −7.92±0.07 and log₁₀ K*_sp,Lu(OH)3 = −23.37±0.14. Individual solubility values for pC _H range between the beginning of precipitation and 8.5 were S _Lu3+ = 3.5·10⁻⁷ mol·dm⁻³, S _Lu(OH)2+ = 6.2·10⁻⁷ mol·dm⁻³, and then total solubility was 9.7·10⁻⁷ mol·dm⁻³.     

Studies on separation of no-carrier-added 177W from bulk lutetium

Irradiation of natural lutetium oxide target with ⁷Li beam results in the formation of no-carrier-added ¹⁷⁷W radionuclide in the matrix. An efficient radiochemical procedure for the separation of no-carrier-added (nca) ¹⁷⁷W (T _1/2 = 2.21 h) radionuclide is presented using liquid-liquid extraction (LLX). A high separation factor between nca ¹⁷⁷W from the target Lu has been achieved with 0.1 M TOA and 8 M HCl. About 85% of ¹⁷⁷W has been extracted in the organic phase keeping Lu in the aqueous phase in a single run. Using this production and separation method radiochemically pure ¹⁷⁷W can be obtained. The separation has also been tried with a greener approach viz. aqueous biphasic extraction. In this case, aqueous biphasic extraction is not a good method for separation of ¹⁷⁷W. The radionuclide ¹⁷⁷W thus obtained can be used to study the extraction pattern of lighter homologue of the element 106 (Sg) together with Mo, which in turn is important to investigate the chemistry of Sg.     

Alternative chromatographic processes for no-carrier added 177Lu radioisotope separation Part I. Multi-column chromatographic process for clinically applicable

The conventional multi-column solid phase extraction (SPE) chromatography technique using di-(2-ethylhexyl)orthophosphoric acid (HDEHP) impregnated OASIS-HLB sorbent based SPE resins (OASIS-HDEHP) was developed for the separation of no-carrier added (n.c.a) ¹⁷⁷Lu from the bulk quantity of ytterbium target. This technique exploited the large variation of lutetium metal ion distribution coefficients in the varying acidity of the HCl solution-OASIS-HDEHP resin systems for the consecutive loading-eluting cycles performed on different columns. The production batches of several hundred mCi n.c.a ¹⁷⁷Lu radioisotope separated from 50 mg Yb target activated in a nuclear reactor of medium neutron flux (Φ = 5·10¹³ n·cm⁻²·s⁻¹) were successfully performed using the above mentioned separation technique. With the target irradiation in a reactor of thermal neutron flux Φ = 2·10¹⁴ n·cm⁻²·s⁻¹ or the parallel run of several separation units, many Ci-s of n.c.a ¹⁷⁷Lu can be profitably produced. The OASIS-HDEHP resin based multi-column SPE chromatography technique makes the separation process simple and economic and offers an automation capability for operation in highly radioactive hazardous environments.     

Recent developments in the manufacture of 173lutetium targets

To better model nuclear processes there is an interest in measuring neutron capture cross sections of lanthanide radioisotopes. A natural hafnium target was irradiated with 100 meV protons at the Los Alamos Isotope Production Facility at the Los Alamos Neutron Science Center (LANSCE) to produce neutron poor lutetium radioisotopes. After irradiation, the target was allowed to cool to allow shorter lived lutetium isotopes to decay. This left predominately ¹⁷³Lu with small amounts of ¹⁷⁴Lu. The hafnium target was then chemically processed to isolate the lanthanide fraction through ion exchange techniques. Recent efforts have focused on the separation of lanthanide species to produce an elementally pure lutetium product, the manufacture of small high density lutetium targets, and neutron capture cross section measurements.     

Volatile organic compounds sensing properties of tetrakis(alkylthio)-substituted lutetium(III) bisphthalocyanines thin films

The effect of volatile organic compounds (VOCs) such as acetone, methanol, ethanol, chloroform, carbon tetrachloride, dichloromethane, and hexane on electrical conductivity of thin films of bis[tetrakis(alkylthio)phthalocyaninato]lutetium(III) double decker complexes [(C_nH_2n+1S)₄Pc]₂Lu(III) was investigated. The [(C_nH_2n+1S)₄Pc]₂Lu(III) molecules substituted with different alkylthia chains (n = 6, 8, 10, 12, and 16) were coated on interdigital transducers using a jet spray technique. A change (increase or decrease) in the conductivity of the [(C_nH_2n+1S)₄Pc]₂Lu(III) films was observed depending on the concentration of the VOCs, which was ranging from 500 to 5000 ppm. The decrease in the conductivity of the sensors for the dissolvent of the compounds (chloroform, carbon tetrachloride, dichloromethane and hexane) could be related to swelling of the films. On the other hand, the increase in the conductivity of the sensors for the other VOCs (acetone, methanol and ethanol) could be resulted from that the VOCs act as electron donors and/or acceptors in the films. A linear relationship between the sensor response and concentration of the VOC vapors is obtained. The sensitivities of the [(C_nH_2n+1S)₄Pc]₂Lu(III) films were in the range of 2.10⁻⁴-3.10⁻³%/ppm.     

Recovery of 177Lu from Irradiated HfO2 Targets for Nuclear Medicine Purposes

A new method of production of one of the most widely used isotopes in nuclear medicine, ¹⁷⁷Lu, with high chemical purity was developed; this method includes irradiation of the HfO₂ target with bremsstrahlung photons. The irradiated target was dissolved in HF and then diluted and placed onto a column filled with LN resin. Quantitative sorption of ¹⁷⁷Lu could be observed during this process. The column later was rinsed with the mixture of 0.1 M HF and 1 M HNO₃ and then 2 M HNO₃ to remove impurities. Quantitative desorption of ¹⁷⁷Lu was achieved by using 6 M HNO₃. The developed method of ¹⁷⁷Lu production ensures high purification of this isotope from macroquantities of hafnium and zirconium and radioactive impurities of carrier-free yttrium. The content of ^177mLu in ¹⁷⁷Lu in photonuclear production was determined. Due to high chemical and radionuclide purity, ¹⁷⁷Lu obtained by the developed method can be used in nuclear medicine.     

Low-temperature heat capacity and high-temperature thermal behavior of sodium lutetium molybdate phosphate Na<Subscript>2</Subscript>Lu(MoO<Subscript>4</Subscript>)(PO<Subscript>4</Subscript>)

The low-temperature heat capacity of Na₂Lu (MoO₄)(PO₄) was measured by adiabatic calorimetry in the range of 7.47–345.74 K. The experimental data were used to calculate the thermodynamic functions of Na₂Lu (MoO₄)(PO₄). At 298.15 K, the following values were obtained: C _p ⁰ (298.15 K) = 237.7 ± 0.1 J/(K mol), S ⁰(298.15 K) = 278.1 ± 0.8 J/(K mol), H ⁰(298.15 K) ? H ⁰ (0 K) = 42330 ± 20 J/mol, and Φ⁰(298.15 K) = 136.1 ± 0. 3 J/(K mol). A heat capacity anomaly was found in the range of 10-67 K with a maximum at T _tr = 39.18 K. The entropy and enthalpy of transition are ΔS = 12.39 ± 0.75 J/(K mol) and ΔH = 403 ± 16 J/mol. The thermal investigation of sodium lutetium molybdate phosphate in the high-temperature range (623–1223 K) was performed using differential scanning calorimetry. It was found that during melting in the range of 1030–1200 K, Na₂Lu(MoO₄)(PO₄) degrades to simpler compounds; the degradation scenario is verified by X-ray powder diffraction.     

Separation of Yb as YbSO4 from the 176Yb target for production of 177Lu via the 176Yb(n, γ)177Yb→177Lu process

An effective and simple process for the separation of ¹⁷⁷Lu from neutron-irradiated Yb targets was developed. Irradiated Yb target was dissolved in H₂SO₄ solution and after reduction with sodium amalgam Yb was precipitated in the form of YbSO₄. From 50 mg of Yb irradiated target only 1 mg Yb remains in solution after precipitation and separation of YbSO₄. The overall recovery of ¹⁷⁷Lu is estimated at 73%. Further efficient chromatographic separation of carrier-free ¹⁷⁷Lu from 1 mg of Yb is relatively easy and is described in several papers.     

A direct hydrogen-1, carbon-13, and nitrogen-15 NMR study of lutetium(III)-isothiocyanate complexation in aqueous solvent mixtures

A direct, low-temperature hydrogen-1, carbon-13, and nitrogen-15 nuclear magnetic resonance study of lutetium(III)-isothiocyanate complex formation in aqueous solvent mixtures has been completed. At –100°C to –120°C in water-acetone-Freon mixtures, ligand exchange is slowed sufficiently to permit the observation of separate¹H,¹³C, and¹⁵N NMR signals for coordinated and free water and isothiocyanate ions. In the¹³C and¹⁵N spectra of NCS^–, resonance signals for five complexes are observed over the range of concentrations studied. The¹³C chemical shifts of complexed NCS^– varied from –0.5 ppm to –3 ppm from that of free anion. For the same complexes, the¹⁵N chemical shifts from free anion were about –11 ppm to –15 ppm. The magnitude and sign of the¹⁵N chemical shifts identified the nitrogen atom as the binding site in NCS^–. The concentration dependence of the¹³C and¹⁵N signal areas, and estimates of the fraction of anion bound at each NCS^–:Lu³⁺ mole ratio, were consistent with the formation of [(H₂O)₅Lu(NCS)]²⁺ through [(H₂O)Lu(NCS)₅]^2–. Although proton and/or ligand exchange and the resulting bulk-coordinated signal overlap prevented accurate hydration number measurements, a good qualitative correlation of the water¹H NMR spectral results with those of¹³C and¹⁵N was possible.     

Microwave-assisted synthesis of phthalocyanine-porphyrin complex and its photoelectric conversion properties

A soluble phthalocyanine-porphyrin complex (Lu(TBPor)Pc) has been rapidly synthesized from a lutetium porphyrin (Lu(TBPor)OAc) and a metal-free phthalocyanine (H₂(TBPc)) under microwave irradiation. Its photoelectric conversion properties have also been investigated. The experimental results reveal that Lu(TBPor)Pc exhibits better photoelectric conversion effect than Lu(TBPor)OAc, H₂(TBPc), and Lu(TBPor)OAc/H₂(TBPc) blend. Furthermore, we have also introduced a n-type photoconductor (N,N′-bis(1,5-dimethylhexyl)-3,4:9,10-perylenebis(dicarboximide)(PDHEP)) and TiO₂ into Lu(TBPor)Pc photoelectric cell to fabricate a SnO₂/Lu(TBPor)Pc + PDHEP + TiO₂/Al photoelectric cell, exhibiting the largest short-circuit photocurrent (691.3μA/cm²) among all of lab-made cells under illumination of white light (1.2 mW/cm²).     

The composition of saturated and superheated vapors and molecular structure of Lu(C5O2HF6)3

The molecular structure of lutetium tris-hexafluoroacetylacetonate Lu(hfa)₃ was studied in a synchronous electron diffraction and mass spectrometric experiment and quantum-chemically by the HF and DFT/B3LYP methods. Saturated vapor over Lu(hfa)₃ was found to be oligomerized to a substantial extent. The mass spectrum of saturated Lu(hfa)₃ vapor was studied over the temperature range 76–100°C; it contained peaks of ions with one to three metal atoms. The peak of the highest intensity corresponded to the M₂L ₅ ⁺ stoichiometry. It was found in experiments with vapor superheating in a double two-temperature effusion cell that oligomeric forms disappeared above 150°C, whereas the decomposition of the monomeric form became noticeable above 250°C. The results obtained in theoretical and experimental studies allowed us to determine the structure of the Lu(hfa)₃ molecule.     

Lanthanide(III) Nitrate Complexes of Two 17 Membered N3O2-Donor Macrocycles

The interaction of lanthanide(III) ions with two N₃O₃-macrocycles, L¹ and L², derived from 2,6-bis(2-formylphenoxymethyl)pyridine and 1,2-diaminoethane has been investigated. Schiff-base macrocyclic lanthanide(III) complexes LnL¹(NO₃)₃ · xH₂O (Ln = Nd, Sm, Eu or Lu) have been prepared by direct reaction of L¹ and the appropriate hydrated lanthanide nitrate. The direct reaction between the diamine macrocycle L² and the hydrated lanthanide(III) nitrates yields complexes LnL²(NO₃)₃· H₂O only for Ln = Dy or Lu. The reduction of the Schiff-base macrocycle decreases the complexation capacity of the ligand towards the Ln(III) ions. The complexes have been characterised by elemental analysis, molar conductivity data, FAB mass spectrometry, IR and, in the case of the lutetium complexes, ¹H NMR spectroscopy.     

On the practical aspects of large-scale production of 177Lu for peptide receptor radionuclide therapy using direct neutron activation of 176Lu in a medium flux research reactor: the Indian experience

This paper accentuates on the practical aspects and intricate technicalities involved in the large-scale production of ¹⁷⁷Lu with specific activity >740 GBq mg^?1 following (n,γ)¹⁷⁷Lu route in a medium flux (~1.2 × 10¹⁴ n cm^?2 s^?1 thermal neutron) research reactor. The implication of target burn-up on the specific activity of ¹⁷⁷Lu during irradiation was discussed in detail. ¹⁷⁷Lu obtained from this route has been extensively utilized for targeted therapy in patients with neuroendocrine tumor in India. The important details available from our experience, as well as technical know-how, would be of considerable value for institutions planning to pursue ¹⁷⁷Lu production through (n,γ)¹⁷⁷Lu route.     

Measurement of Electron Affinity of Atomic Lutetium via the Cryo-SEVI Method

Electron affinities (EAs) of most lanthanide elements still remain unknown due to their relatively low EA values. In the present work, the cryogenically controlled ion trap is used for accumulating atomic lutetium anion Lu^-, which makes the measurement of electron affinity of lutetium become practicable. The high-resolution photoelectron spectra of Lu^- are obtained via the slow-electron velocity-map imaging method. The electron affinity of Lu is determined to be 1926.2(50) cm^-1 or 0.23882(62) eV. In addition, two excited states of Lu^- are observed.     

Accurate determination of half-life and radionuclidic purity of reactor produced <Superscript>177g</Superscript>Lu (<Superscript>177m</Superscript>Lu) for metabolic radiotherapy

Thanks to its favorable decay characteristics, ^177gLu is finding several applications in nuclear medicine, especially for palliative metabolic radiotherapy of cancer and radioimunotherapy. ^177gLu is produced in thermal nuclear reactor either by direct neutron capture ¹⁷⁶Lu(n,γ)^177(m+g)Lu on either natural or enriched ¹⁷⁶Lu target, or by reaction on enriched ¹⁷⁶Yb target followed by negatron decay. The latter method does produce a high radionuclidic purity and high specific activity radionuclide in no-carrier-added form, since ¹⁷⁷Yb decays solely to the ground state ^177gLu. Conversely, the first method does produce a low specific activity ^177gLu in carrier-added form,¹ contaminated by the long-lived radioisotopic impurity ^177mLu. The accurate determination of radionuclidic purity and half-life of ^177gLu carried out by HPGe and LSCS is presented in some details.     

Reactor produced 177Lu of specific activity and purity suitable for medical applications

Four production methods of ¹⁷⁷Lu, e.g. from natural and enriched Lu and from natural and enriched Yb were considered and experimentally evaluated. The samples of all 4 materials were irradiated in a nuclear reactor, the activity of ¹⁷⁷Lu measured and compared with a computed one. In the case of ¹⁷⁷Lu produced from enriched Lu target the amount of activity obtained is 40 to 70% higher than calculated. The results achieved will be applied for the optimization of ¹⁷⁷Lu production for medical applications.