The determination of radium-226 and radium-228 in soils and plants,using radium-225 as a yield tracer

Recovery of²²⁶Ra in analysis is determined using²²⁵Ra separated by anion exchange from²²⁹Th and²³³U. Radium is coprecipitated with barium, and purified by ion exchange.²²⁶Ra and²¹⁷At (decay product of²²⁵Ra) are measured by α-spectrometry.²²⁸Ra is determined both by β-counting²²⁸Ac and²²⁵Ac separated from²²⁸Ra and²²⁵Ra, and by α-counting its daughters after the decay of²²⁵Ra. Sources for α-spectrometry are prepared by electrodeposition (molecular plating).     

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.     

The use of 15N-NMR spectroscopy for assigning the structures of isomeric N7- and N9-substituted purines

An ¹⁵N-NMR study has shown a considerable difference in electronic structures between the isomeric N⁷ and N⁹ substituted purines. A comparison of ¹⁵N chemical shifts amongst the seven pairs of N⁷ and N⁹ isomers has revealed that (1) the N³ resonances are shielded by 18–20 ppm in an N⁹ isomers; (2) the amino nitrogens at the C-2 or at C-6 positions are always shielded by 3–4 ppm in the N⁷ isomers; (3) the N⁷ chemical shifts in the N⁷ isomers are always more shielded by 6–7 ppm than the N⁹ resonances in the N⁹ isomers. It has a also been found by protonation studies that the N⁹ of the N⁷ isomer is much more basic than the N⁷ of the N⁹ isomer.     

Rapid determination of 89Sr and 90Sr in radioactive waste using Sr extraction disk and beta-ray spectrometer

A rapid determination method in which beta-ray spectrometry was combined with solid phase extraction using Sr Rad Disk was developed for the determination of ⁸⁹Sr and ⁹⁰Sr in low-level radioactive waste. Various amounts of ⁸⁹Sr, ⁹⁰Sr, and ⁹⁰Y retained by the Sr Rad Disk was measured by a beta-ray spectrometer, and it was found that both ⁸⁹Sr and ⁹⁰Sr were simultaneously determined with <30% error (2σ) at ⁸⁹Sr/⁹⁰Sr radioactivity ratio of 0.3 to 45. The present method was successfully applied to actual radioactive liquid waste samples arising from nuclear facilities in Japan Atomic Energy Agency. Strontium was simply separated from interfering nuclides such as ¹³⁷Cs and ¹⁵⁴Eu, and matrix components by the Sr Rad Disk, and the results obtained by beta-ray spectrometry was in good agreement with that of the conventional analysis.     

Energy-transfer processes in decaying helium-cadmium plasmas

Light absorption and emission spectroscopy were used in studies of the time dependences of the CdII spectral emission and He^m(2³S) number density in the stationary afterglow of helium-cadmium mixtures. Transitions from 12 CdII energy levels were monitored in the afterglow. The five CdII states below 20 eV are produced, either directly or via cascading, by the Penning ionization of Cd by He^m(2³S). The remaining CdII states studied are produced by the chargeexchange excitation of Cd by He⁺. No evidence was found for the production of CdII energy levels by charge transfer between Cd and He ₂ ⁺ or by Penning ionization of Cd by He ₂ ^m (2³ _u ⁺ ). A value of (5.4±0.3)×10^–10 cm³ sec^–1 was measured for the reaction rate coefficient for the Penning ionization of Cd by He^m(2³S), and a value of (2.1±0.2)×10^–10 cm³ sec^–1 was measured for the reaction rate coefficient for charge exchange between He⁺ and Cd at a gas temperature of 200°C.     

Adsorption of fission products on a metal surface in nitric acid solutions: Radiochemical study using a multitracer

Adsorption behavior of fission products in nitric acid solution on various alloys and metals was studied by using a multitracer produced by neutron irradiation of UO₂. The adsorption behavior of the fission products ⁹⁹Mo, ¹³¹I, ¹³²Te, ¹⁴⁰La, and ¹⁴³Ce, and ²³⁹Np was simultaneously studied. Some chemical decontamination tests were also examined. Clear adsorption of ⁹⁹Mo, ¹³¹I, and ¹³²Te was observed, whereas adsorption of ¹⁴⁰La, ¹⁴³Ce, and ²³⁹Np was not. The adsorption characteristics were discussed by considering anion-exchange reaction and surface complexation.     

Convenient preparative synthesis of pentacyclo[5.3.0.02,5.03,9.04,8]decane (<Emphasis Type="Italic">C</Emphasis><Subscript>2</Subscript>-Bishomocubane)

By reaction of pentacyclo[5.3.0.0^2,5.0^3,9.0^4,8]decane-6,10-dione 6-ethyleneketal with lithium aluminum hydride the corresponding hydroxyketal was obtained whose hydroxy group was replaced by chlorine at boiling in CCl₄ in the presence of a 15% molar excess of triphenylphosphine. 6-Ethyleneketal of pentacyclo-[5.3.0.0^2,5.0^3,9.0^4,8]decan-6-one obtained by dechlorination of the chloroketal in a system lithium-t-BuOH in THF was hydrolyzed to ketone by heating in 10% sulfuric acid in the presence of THF. The obtained ketone was reduced along Wolf-Kishner reaction to pentacyclo[5.3.0.0^2,5.0^3,9.0^4,8]decane.     

Studies of the vertical distribution of134Cs,137Cs,238Pu,239, 240Pu,241Pu,241Am and210Pb in ombrogenous mires at mid-latitudes

Six peat cores taken from three unmodified blanket and raised bogs in Ireland were sectioned and analyzed for a range of radionuclides including¹³⁴Cs,¹³⁷Cs,²³⁸Pu,²³⁹Pu,²⁴¹Am, and²¹⁰Pb.¹³⁴Cs and¹³⁷Cs were measured by high resolution gamma-spectrometry, while the transuranium nuclides were determined after chemical separation by alpha-spectrometry.²⁴¹Pu, present on the electroplated discs together with Pu(), was measured directly by low-level liquid scintillation counting. Core chronologies were established by measuring the unsupported²¹⁰Pb component using low energy photon spectrometry (LEPS). From the resulting profiles, relaxation depths and migration rates for the above mentioned radionuclides have been determined and differences in the values of these parameters interpreted.²³⁸Pu/^239,240Pu and²⁴¹Pu/^239,240Pu ratios have been examined carefully and are discussed in some detail. Finally, the contribution from Chernobyl to the total radiocaesium inventory in each core has been established using the¹³⁴Cs/¹³⁷Cs ratio observed in the initial fallout from Chernobyl.     

Migration mechanisms of 237Np and 241Am through loess media

Migration experiments with ²³⁷Np(V) and ²⁴¹Am(III) have been performed using a column system, packed with loess, taken from Shanxi, China. The adsorption mechanism of ²³⁷Np and ²⁴¹Am on the loess was examined by a chemical extraction method. Most of ²³⁷Np was adsorbed on the influent edge of the column, and the adsorbtion was mainly controlled by surface complexation. However, the migration of ²³⁷Np in loess media could be roughly evaluated by the distribution coefficient. In the case of ²⁴¹Am, particulate, the ²⁴¹Am species was formed in the influent solution and moved in the column. The ²⁴¹Am adsorbed on loess was controlled by irreversible reactions. The migration behavior of particulate ²⁴¹Am in loess media could be expressed by the filtration theory.     

On the Remarkable Role of the Nitrogen Ligand in the Gas‐Phase Redox Reaction of the N2O/CO Couple Catalyzed by [NbN]+

The thermal gas‐phase catalytic reduction of N₂O by CO, mediated by the transition‐metal nitride cluster ion [NbN]⁺, has been explored by using FT‐ICR mass spectrometry and complemented by high‐level quantum chemical calculations. In contrast to the [Nb]⁺/[NbO]⁺ and [NbO]⁺/[Nb(O)₂]⁺ systems, in which the oxidation of [Nb]⁺ and [NbO]⁺ with N₂O is facile, but in which neither [NbO]⁺ nor [Nb(O)₂]⁺ react with CO at room temperature, the [NbN]⁺/[ONbN]⁺ system at ambient temperature mediates the catalytic oxidation of CO. The origins of the distinctly different reactivities upon nitrogen ligation are addressed by quantum chemical calculations.     

Emissive Synthetic Cofactors: Enzymatic Interconversions of tzA Analogues of ATP,NAD+, NADH,NADP+, and NADPH

A series of enzymatic transformations, which generate visibly emissive isofunctional cofactors based on an isothiazolo[4,3‐d]pyrimidine analogue of adenosine ( ^tz A ), was developed. Nicotinamide adenylyl transferase condenses nicotinamide mononucleotide and ^tz ATP to yield N^tzAD⁺ , which can be enzymatically phosphorylated by NAD⁺ kinase and ATP or ^tz ATP to the corresponding N^tzADP⁺ . The latter can be engaged in NADP‐specific coupled enzymatic transformations involving conversion to N^tzADPH by glucose‐6‐phosphate dehydrogenase and reoxidation to N^tzADP⁺ by glutathione reductase. The N^tzADP⁺ / N^tzADPH cycle can be monitored in real time by fluorescence spectroscopy.     

Natural radionuclide-free phosphoric acid production

High-uranium phosphate rock from Itataia, Brazil, was milled for wet-process phosphoric acid production using the dihydrate method. Uranium contained in the phosphoric acid was recovered by solvent extraction. The distribution of long-lived natural radionuclides of the ²³⁸U and ²³²Th decay series involved in these operations was evaluated. ²²⁶Ra, ²²⁸Ra and ²¹⁰Pb were found to predominate in the phosphogypsum, while ²²⁸Th, ²³⁰Th and ²³²Th in the uranium-free phosphoric acid. Thorium is removed from the phosphoric acid by solvent extraction to produce a NORM-free phosphoric acid.     

Measurement of lead-210, bismuth-210, and polonium-210 in environmental samples

Mathematical equations governing the ratio of²¹⁰Bi/²¹⁰Pb and²¹⁰Po/²¹⁰Pb activities are used to explain the ingrowth of²¹⁰Bi and²¹⁰Po in environmental samples during post collection. Procedures are described for radiochemical separation of²¹⁰Pb,²¹⁰Bi, and²¹⁰Po in a state of radioactive disequilibrium and quantification by alpha- and beta-counting. Also, the special case is considered where²¹⁰Bi is in equilibrium with²¹⁰Pb, but both are in disequilibrium with²¹⁰Po. In this case, the activities of both²¹⁰Pb and²¹⁰Po are computed by measuring²¹⁰Po activity twice, using alpha-counting.     

Radiochemical determination of 90Sr and 86Sr in soil

Summary A modified HCl-leach method for the radiochemical ⁹⁰Sr and ⁸⁹Sr determination in soil has been developed. The sample is leached by HCl in the presence of the Sr-carrier. Then bi- and trivalent ions are separated by a combination of complexation and ion exchange. The separation of strontium and calcium is performed by fuming nitric acid. After further purification, strontium carbonate is precipitated and the activity of ⁹⁰Sr and ⁸⁹Sr is measured. ⁹⁰Sr determined by the isolation of ⁹⁰Y and by measuring its activity. The ⁹⁰Sr and ⁸⁹Sr content in soil is calculated from the measured activities of yttrium oxide and strontium carbonate by considering the counting efficiencies for ⁹⁰Y, ⁹⁰Sr and ⁸⁹Sr beta rays, the chemical yields of strontium and yttrium and the time of ⁹⁰Y growth from ⁹⁰Sr.

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Radiochemische Bestimmung von ⁹⁰Sr und ⁸⁹Sr in Boden

Zusammenfassung Eine modifizierte Auslaugungsmethode für die radiochemische Bestimmung von ⁹⁰Sr und ⁸⁹Sr im Boden wurde entwickelt. Die Probe wird in HCl in Gegenwart des Sr-Trägers ausgelaugt und die zwei- und dreiwertigen Ionen dann durch eine Kombination von Komplexierung und Ionenaustausch getrennt. Die Strontiumtrennung von Calcium erfolgt mit rauchender Salpetersäure. Nach weiterer Reinigung wird SrCO₃ gefällt und die Aktivität von ⁹⁰Sr und ⁸⁹Sr bestimmt. ⁹⁰Sr wird durch Isolierung und Zählung von ⁹⁰Y ermittelt. Der ⁹⁰Sr- und ⁸⁹-Sr-Gehalt im Boden wird aus der Aktivität von Y₂O₃ und SrCO₃ unter Berücksichtigung der Zählausbeute für ⁹⁰Y-, ⁹⁰Sr- und ⁸⁹-Sr-beta-Strahlen, aus der gravimetrischen Bestimmung von Strontium und Yttrium und aus der Zeit der ⁹⁰Y-Entstehung aus ⁹⁰Sr bestimmt.

     

Positive-ionization decay of the carbon k-shell excited negative-ion resonance in co

The resonant state CO-(Cls)^-1 (2pπ)². first reported by King has been observed to decay by multiple Auger effect in all the positive-ionization channels of CO. The relative abundances for the resonant formation of CO⁺. CO²⁺. C⁺. O⁺, C²⁺ ions have been measured. the decay to neutral states by normal Auger transitions is observed in the (O- + C⁺ ion-pair formation.     

A molecular fluorophore in citric acid/ethylenediamine carbon dots identified and quantified by multinuclear solid-state nuclear magnetic resonance

The composition of fluorescent polymer nanoparticles, commonly referred to as carbon dots, synthesized by microwave-assisted reaction of citric acid and ethylenediamine was investigated by ¹³C, ¹³C{¹H}, ¹H─¹³C, ¹³C{¹⁴N}, and ¹⁵N solid-state nuclear magnetic resonance (NMR) experiments. ¹³C NMR with spectral editing provided no evidence for significant condensed aromatic or diamondoid carbon phases. ¹⁵N NMR showed that the nanoparticle matrix has been polymerized by amide and some imide formation. Five small, resolved ¹³C NMR peaks, including an unusual ═CH signal at 84 ppm (¹H chemical shift of 5.8 ppm) and ═CN₂ at 155 ppm, and two distinctive ¹⁵N NMR resonances near 80 and 160 ppm proved the presence of 5-oxo-1,2,3,5-tetrahydroimidazo[1,2-a]pyridine-7-carboxylic acid (IPCA) or its derivatives. This molecular fluorophore with conjugated double bonds, formed by a double cyclization reaction of citric acid and ethylenediamine as first shown by Y. Song, B. Yang, and coworkers in 2015, accounts for the fluorescence of the carbon dots. Cross-peaks in a ¹H─¹³C HETCOR spectrum with brief ¹H spin diffusion proved that IPCA is finely dispersed in the polyamide matrix. From quantitative ¹³C and ¹⁵N NMR spectra, a high concentration (18 ± 2 wt%) of IPCA in the carbon dots was determined. A pronounced gradient in ¹³C chemical-shift perturbations and peak widths, with the broadest lines near the COO group of IPCA, indicated at least partial transformation of the carboxylic acid of IPCA by amide or ester formation.     

Ammonolysis of 1,2‐Bis[dichloro(methyl)silyl]ethane. On the Structure of 1,3,6,8‐Tetramethyl‐2,7,11,12‐tetraaza‐1,3,6,8‐tetrasila‐tricyclo[6.2.1.13,6]‐dodecane

Ammonolysis of 1,2‐bis[dichloro(methyl)silyl]ethane afforded a crystalline tricyclic silazane along with polymeric material. The crystalline material could be isolated in pure state. It was analyzed by ¹H, ¹³C, ¹⁵N and ²⁹Si NMR spectroscopy in solution, by ¹³C, ¹⁵N and ²⁹Si MAS NMR spectroscopy in the solid state, as well as by single‐crystal and powder X‐ray diffraction. The title compound exists as a single isomer in solution, whereas in the solid state the presence of several modifications is indicated, in particular by the solid‐state MAS NMR spectra.     

A device for uranium series leaching from glass fiber in HEPA filter

For the disposal of a high efficiency particulate air (HEPA) glass filter into the environment, the glass fiber should be leached to lower its radioactive concentration to the clearance level. To derive an optimum method for the removal of uranium series from a HEPA glass fiber, five methods were applied in this study. That is, chemical leaching by a 4.0?M HNO₃?C0.1?M Ce(IV) solution, chemical leaching by a 5 wt% NaOH solution, chemical leaching by a 0.5?M H₂O₂?C1.0?M Na₂CO₃ solution, chemical consecutive chemical leaching by a 4.0?M HNO₃ solution, and repeated chemical leaching by a 4.0?M HNO₃ solution were used to remove the uranium series. The residual radioactivity concentrations of ²³⁸U, ²³⁵U, ²²⁶Ra, and ²³⁴Th in glass after leaching for 5?h by the 4.0?M HNO₃?C0.1?M Ce(IV) solution were 2.1, 0.3, 1.1, and 1.2?Bq/g. The residual radioactivity concentrations of ²³⁸U, ²³⁵U, ²²⁶Ra, and ²³⁴Th in glass after leaching for 36?h by 4.0?M HNO₃?C0.1?M Ce(IV) solution were 76.9, 3.4, 63.7, and 71.9?Bq/g. The residual radioactivity concentrations of ²³⁸U, ²³⁵U, ²²⁶Ra, and ²³⁴Th in glass after leaching for 8?h by a 0.5?M H₂O₂?C1.0?M Na₂CO₃ solution were 8.9, 0.0, 1.91, and 6.4?Bq/g. The residual radioactivity concentrations of ²³⁸U, ²³⁵U, ²²⁶Ra, and ²³⁴Th in glass after consecutive leaching for 8?h by the 4.0?M HNO₃ solution were 2.08, 0.12, 1.55, and 2.0?Bq/g. The residual radioactivity concentrations of ²³⁸U, ²³⁵U, ²²⁶Ra, and ²³⁴Th in glass after three repetitions of leaching for 3?h by the 4.0?M HNO₃ solution were 0.02, 0.02, 0.29, and 0.26?Bq/g. Meanwhile, the removal efficiencies of ²³⁸U, ²³⁵U, ²²⁶Ra, and ²³⁴Th from the waste solution after its precipitation?Cfiltration treatment with NaOH and alum for reuse of the 4.0?M HNO₃ waste solution were 100, 100, 93.3, and 100%.     

Purification of 89Sr source obtained from 89Y(n,p) 89Sr by ion-exchange chromatography using tri-sodium tri-meta phosphate (SMP) as eluant

⁸⁹Sr was produced via ⁸⁹Y(n, p) ⁸⁹Sr using yttria as target in Fast Breeder Test Reactor (FBTR), Kalpakkam, India. A radiochemical procedure has been developed for the separation of bulk yttrium using TBP by solvent extraction followed by purification of ⁸⁹Sr source by ion exchange chromatography using the cation exchange resin Dowex 50WX8 (100–200 mesh) and nitric acid of variable molarity as eluant. The present study establishes the purification of ⁸⁹Sr source from the other radionuclidic impurities like ⁸⁸Y, ⁶⁵Zn, ⁵⁴Mn, ⁶⁰Co, ⁸⁶Rb, ¹⁹²Ir, ¹⁰³Ru, ¹¹³Sn, ¹³⁹Ce, ¹⁶⁰Tb, ¹⁵⁴Eu etc. produced during the irradiation of yttria by using the complexing agent tri-sodium tri-meta phosphate (SMP) in nitric acid medium instead of nitric acid alone as an eluant. The purification was achieved by using 0.1 M SMP as complexing agent which was optimized based on the distribution ratio data and final elution of Sr fraction was obtained in nitric acid medium. This resulted into a faster purification of ⁸⁹Sr source in a smaller volume of eluant. Purity of Sr source from the cross contamination of the complexing agent SMP was also ensured.