Distribution of minor and trace elements among some Italian chondritic meteorites

The cobalt, nickel, zinc, selenium, rubidium and cesium content was determined in eight Italian chondritic meteorites by destructive neutron activation analysis. The chemical procedure involves only a few steps: sample dissolution, radiochemical separation of the elements on inorganic adsorbers (copper grains and zinc ferrocyanide) and on Dowex 2×8 anionic resin. Element contents are reported and discussed. Precision and accuracy of the analytical method are given as well. Results and average class values are compared with existing values in the literature. Possible correlations between pairs of elements (Co−Ni, Zn−Se and Rb−Cs) in the examined chondrites were investigated and discussed.     

Gas-phase catalytic oxidation ofm-xylene

The gas-phase oxidation ofm-xylene on catalysts for partial hydrocarbon oxidation (Bi−Fe−Co−Ni−Mo−P−O, V−Sb−O and V−Ti−O) has been studied at 325–400°C. 3-Methylbenzaldehyde (for the first two catalysts), or both 3-methylbenzaldehyde and 3-methylbenzoic acid (for the last one) were shown to be the main partial oxidation products.     

Error estimation of the single comparator method due to uncertainties of literature data for thermal and epithermal neutron activation cross-sections

The reliability of the single comparator method depends mainly on the accuracy of k factors. This paper describes error in theoretical k factors, especially that due to the scattering in literature data for thermal and epithermal neutron activation cross-sections. Error calculations were performed for thirteen elements using comparator sets of⁶⁰Co−¹⁹⁸Au and⁹⁵Zr−⁹⁷Zr to evaluate the accuracy of this method.     

Separation of metal ions by different stationary extraction zones on a glass paper

A separation method using some extraction zones consisting of different organic extractants adsorbed on a sheet of supporting material, has been devised for separation of metal involving radionuclides. Glass paper is the best support to retain liquid extractants zonally, so as not to mix, and TBP, TOPO and TOA retained on it, are employed as example. After feeding of metal ions and washing with developing solution by the descending technique, each element is retained by an appropriate extraction zone, and detection and determination are carried out radiometrically. Separations of Sn−Cd−Bi−As, Sn−Cd−Ag, Fe−Co−Zn and Sn−Sb−Bi in 2M HCl system are demonstrated.     

Co?Cu?Al mixed oxides derived from hydrotalcite-like compound for NO reduction by CO

Various hydrotalcite based catalysts were prepared for catalytic removal of NO (NO reduction by CO). The general formula of hydrotalcite compounds (HTLc) was Co−Cu−Al-HTLc. Precalcination of these materials at 450°C for NO reduction by CO, was necessary for catalytic activity. All catalysts except Co−Al and Cu−Al have very good activity at lower temperature for NO reduction by CO. All samples were characterized by XRD and BET. The tentative reaction mechanism was also proposed.     

Fabrication and electrochemical properties of novel ternary Sb–Co–P alloy electrodes for lithium-ion batteries

A novel ternary Sb–Co–P alloy electrode was prepared by electroplating on copper current collector as a promising negative electrode material for lithium-ion batteries. The structural and morphological features of the Sb–Co–P alloy were characterized by powder X-ray diffraction (XRD) and scanning electron microscope (SEM). The as-prepared alloy electrode exhibits a high specific capacity and an excellent cycleability. The initial discharge and charge capacities of the Sb–Co–P alloy anode were measured 700 and 539 mA h g⁻¹, respectively. The results suggest that the Sb–Co–P alloy material obtained by the electrodeposition shows a good candidate anode material for lithium-ion batteries.     

Synthesis and structure of μ-oxo-bis-[(2,5-dimethylbenzenesulfonato)tri-p-tolylantimony(v)]

μ-Oxobis[(2,5-dimethylbenzenesulfonato)tri-p-tolylantimony(v)] was prepared by the reaction of 2,5-dimethylbenzesulfonic acid with tri-p-tolylstibine in the presence of hydrogen peroxide. According to X-ray diffraction data, the linear O bridge links two Sb atoms having a trigonal bipyramidal configuration. The 2,5-dimethylbenzenesufonate group and the bridging O atom occupy the axial positions and the three tolyl substituents are equatorial. The Sb(1)−O−Sb(2) and O−Sb−O angles are 180.0(0)° and 177.2(1)°; the Sb−C(Ph)_eq, Sb−O(SO₂Ar), and Sb−μ−O distances are 2.090(5)–2.095(6), 2.258(3), and 1.9361(5), respectively. Translated fromIzvestiya Akademii Nauk. Seriya Khimicheskaya, No. 12, pp. 2346–2349, December, 1999.     

Analytical use of neutron-capture gamma-rays

Certain elements which are not possible to detect with conventional neutron activation analysis can be measured using thermal neutron-capture gamma-ray analysis. The use of a curved neutron guide at the High Flux Reactor, Grenoble, with a thermal neutron flux of 1.5·10¹⁰n·cm⁻²·sec⁻¹ and the advantage of a low-background counting system (Ge(Li) detector) far from the reactor core are described. Experimental detection limits of a number of elements are given for the low-energy and the high-energy regions. Some applications of the capture gamma-ray method in the whole energy range are studied and are briefly discussed.     

Sur l'application de la chromatographie sur colonne de cellulose naturelle impregnee d'oxyde de tri-n-octylphosphine a la separation de quelques cations

This paper presents the experimental results of an investigation upon cellulose treated with tri-n-octylphosphine oxide for the column chromatography method used during the activation analysis of metals. The most interesting results are obtained in the separation of Au−Sb−Tl.      

Rare-earth elemental analysis of banded iron-formations by instrumental neutron activation analysis

Representative banded iron-formations (BIFs) from various locations of the eastern Indian geological belt were investigated by instrumental neutron activation analysis (INAA). After pre-concentration, irradiation was carried out using a neutron flux of 5.1·10¹⁶ m⁻²·s⁻¹, 1.0·10¹⁵ m⁻²·s⁻¹ and 3.7·10¹⁵ m⁻²s⁻¹, with thermal, epi-thermal and fast neutrons, respectively. The activities in these samples were measured by a HPGe detector. Ten rare-earth elements, such as La, Ce, Nd, Sm, Eu, Tb, Ho, Tm, Yb and Lu, have been qualitatively identified and quantitatively estimated in these samples. The present investigation is an example of employing a pre-concentration method for high iron-containing ores prior to neutron activation analysis.     

Experimental sensitivities for 3 MeV neutron activation analysis

The experimental sensitivity for 72 different elements using 3 MeV neutron activation has been investigated. Using a 200 kV Cockcroft-Walton neutron generator with a 3 MeV neutron flux of about 1.5·10⁶n·cm⁻²·sec⁻¹, γ-ray spectra of 51 elements were obtained with a sufficient number of photopeak counts for sensitivity calculations using a photopeak integration method. A useful table summarizing the sensitivity results is given. That 3 MeV neutron activation analysis is practical, is demonstrated by the experimental sensitivities obtained. Guest worker from the Institute of Nuclear Techniques, Academy of Mining and Metallurgy, Krakow, Poland, at the National Bureau of Standards, 1968–1969.     

Gamma-ray spectra and sensitivities for 2.8 MeV neutron activation analysis

The use of 2.8 MeV neutrons produced by the D(d, n)³He reaction should be taken into consideration in some applications of radioactivation analysis. The low number of elements activable by these neutrons makes possible to minimize the matrix interference and the background below the characteristic photopeaks. The very low dead-time of the spectrometric measurements permits the use of the maximum neutron flux available now and in the future. The purpose of this paper is to define experimentally the sensitivity of determination for the 16 main elements activable with a 400 keV Van de Graaff accelerator at a 2.8 MeV neutron flux of 2·10⁶ n·cm⁻²·sec⁻¹ on the sample.     

Lower limit of determination values for trace elements in iron certified reference materials by neutron activation analysis with multiple gamma-ray detection

Recycling steel products demands a new technique for determining tramp elements in steel. Tramp elements, As and Sb, in some iron certified reference materials were determined by neutron activation analysis with multiple gamma-ray detection method and reported in MTAA11. In MTAA12, the authors reported the lower limit of determination values (LDL) and the dispersion of this method. The values of the LDLs for As and Sb in high purity iron were 0.002 and 0.0009 μg·g⁻¹. The dispersion is small enough to satisfy the demand from materials science.     

Electrochemical performance of Co–Al layered double hydroxide nanosheets mixed with multiwall carbon nanotubes

Regular hexagonal Co–Al layered double hydroxides (Co–Al LDH) were synthesized by urea-induced homogeneous precipitation. This material proved to be nanosheets by scanning electron microscopy and X-ray diffraction measurements. The electrochemical capacitive behavior of the nanosheets in 1 M KOH solution were evaluated by constant current charge/discharge and cyclic voltammetric measurements, showing a large specific capacitance of 192 F·g⁻¹ even at the high current density of 2 A·g⁻¹. When multiwall carbon nanotubes (MWNTs) were mixed with the Co–Al LDH, it was found that the specific capacitance and long-life performance of all composite electrodes at high current density are superior to pure LDH electrode. When the added MWNTs content is 10 wt%, the specific capacitance increases to 342.4 F·g⁻¹ and remains at a value of 304 F·g⁻¹ until the 400th cycle at 2 A·g⁻¹, showing that this is a promising electrode material for supercapacitors working at heavy load. According to the electrochemical impedance spectra, MWNTs greatly increase the electronic conductivity between MWNTs and the surface of Co–Al LDH, which consequently facilitates the access of ions in the electrolyte and electrons to the electrode/electrolyte interface.     

Studies of the trace element content of bullet lead and jacket material

The technique of instrumental neutron activation analysis, involving neutron fluxes of 10¹⁴ n·cm⁻²·sec⁻¹ and high resolution Ge(Li) gamma-detectors, has been applied to the analysis of bullet lead and jacket material. Radiochemical separation of the majority of the radioantimony from the irradiated bullet material was performed, with the objective of facilitating measurement of other elements present. Eight elements were measured in bullet lead and four in jacket material. Concentration variations between the varieties of ammunition studied indicate that more extensive studies, directed to possible ammunition characterisation, would be worthwhile.     

Gallium determination in biological samples

A sensitive, simple and time-saving method has been developed for the neutron activation analysis of gallium at concentrations around 10⁻⁴ ppm in biological tissues. After a 24-hour irradiation in a thermal neutron flux of 2.8·10¹³ n·cm⁻²·s⁻¹ and a purification by ion-exchange chromatography to eliminate troublesome elements such as sodium, iron and copper, the⁷²Ga activity is measured with enough accuracy for the method to be applicable in animal physiology and clinical toxicology.     

Neutron activation analysis of pure uranium: Preconcentration of impurity elements

We have developed a radiochemical neutron activation analysis technique (RNAA) of pure uranium with using extraction chromatographic separation of ²³⁹Np from impurity elements in TBP-6M HNO₃ media. The estimation of influence of fission products of ²³⁵U on the results by radiochemical neutron activation analysis has been carried out. For it we have performed NAA with preconcentration of impurity elements. Experiments show that in this case the apparent concentration of Y, Zr, Mo, Cs, La, Ce, Pr, Nd exceeds the true concentration by 2500–3000 times. Therefore, determination of these elements is not possible by RNAA. This technique allowed to use the determination of 26 impurity elements with detection limit 10⁻⁵–10⁻⁹% by mass. This developed technique may be used for the determination of impurities in uranium and its compounds.     

A low cost neutron capture prompt gamma-ray analysis facility at a research reactor

A low cost neutron capture prompt gamma activation analysis facility has been constructed at The University of Michigan's Pheonix Memorial Laboratory. Although the neutron beam used has a fairly large epithermal component (Cd ratio 7.1), background levels are low enough to result in satisfactory measurement of over 16 different elements. For the elements of greatest sensitivity (samarium, boron, gadolinium, and cadmium) minimum detectable levels of 3.6·10⁻⁵ to 1.4·10⁻⁵ gram for a one hour measurement are possible. The fast neutrons incident to the detector were found to be minimal. Estimates of up to 3 years of continuous operation before measurable damage is expected.     

Determination of 22 elements in geological samples by instrumental neutron activation analysis

An instrumental neutron activation analysis (INAA) method has been developed for multi-element determination in geological samples. The INAA method consists of irradiation of samples for 90 sec at a flux of 1.0·10¹² n·cm⁻²·sec⁻¹ and determination of 12 elements by using their short-lived nuclides. Samples have been re-irradiated for 3 hrs for measuring concentrations of another 10 elements. Precision and accuracy of the INAA method have been evaluated by analysing samples and USGS standard reference materials. Precision and accuracy are within±15% and ±10%, respectively.     

Investigation of the interaction of Greek dolomitic marble with metal aqueous solutions using rutherford backscattering and X-ray photoelectron spectroscopy

To enhance the applicability of the nuclear analytical technique in the field of industry and the environment, the inorganic elemental content of the bottom ash from a municipal solid waste incinerator was determined by instrumental neutron activation analysis. Bottom ash samples were monthly collected from an incinerator located at a metropolitan city in Korea, strained through a 5 mm sieve, dried by an oven and pulverized by an agate mortar. The samples were irradiated at the NAA #1 irradiation hole (thermal neutron flux: 2.92·10¹³ n·cm⁻²·s⁻¹) in the HANARO research reactor of the Korea Atomic Energy Research Institute and the irradiated samples were measured by a HP Ge gamma-ray spectrometer. Thirty-three elements including As, Cr, Cu, Fe, Mn, Sb and Zn were analyzed by an absolute method. The quality control was conducted by a simultaneous analysis with NIST standard reference materials. The average concentrations of the major elements such as Ca, Fe, Al, Na, Mg, K and Ti measured in the sample were 19.9%, 4.85%, 3.79%, 2.11%, 1.84%, 1.22% and 1.02%, respectively. In addition, the concentrations of the hazardous metals like Zn, Cu, Cr, Sb and As were 0.77%, 0.31%, 729 mg·kg⁻¹, 116 mg·kg⁻¹ and 22.2 mg·kg⁻¹, respectively.