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Abstract  

A method is described to determine traces of V, Fe, Ni, Zn, Nb and Mo in high purity matrices of niobium, tantalum and tungsten by non-destructive 14 MeV3He activation analysis. The influence of nuclear and γ-ray interferences in the determination of these elements is discussed.

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Abstract  

For the first time the chemical identification of element 106 was accomplished. The Gas-thermochromatographic experiments with an oxochloride of element 106 are described. Reproducible zones of tracks of fission fragments were observed in the temperature region of 150–250°C. The chemical behavior of element 106 oxochloride is similar to that of the tungsten compound.

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Abstract  

Procedures are described for determining traces of titanium in scandium, vanadium in titanium, zinc in copper and tungsten in tantalum, utilizing activation with 11 Me V protons. Experimental data on48V,51Cr,66Ga and182Re yields and analytical sensitivities are reported.

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Abstract  

Results of a study of the corrosion of various transition-metal alloys, tantalum, and tantalum/2.5% tungsten are reported. The solvent contained nitric acid, hydrofluoric acid, and ammonium hexanitratocerate. It was designed to imitate the corrosiveness of the nitric acid, hydrofluoric acid mixture used to dissolve 238-plutonium dioxide.

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Abstract  

A unique application of forensic neutron activation analysis involving the analysis of trace levels of tungsten, cobalt and tantalum was presented as evidence in a murder trial. The evidence materials analyzed included the blous of the victim, bed sheets, a pair of pantyhose used in strangulation, head and public hair from the suspect, and several samples of raw materials used at a factory where the suspect was employed. The stalned areas of the fabrics analyzed showed trace levels of cobalt, tantalum, and tungsten which were not present in the fabric mattrices. The occupation of the suspect exposed him to fine dust particulates containing these trace elements. Although eyewitness accounts indicated that the suspect was in the neighborhood, there was, however, no evidence other that the neutron activation analysis results to indicate the probable presence of the suspect at the scence of the crime. A jury trial accepting neutron activation analysis findings resulted in a conviction.

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Abstract  

In recent years chances of using rhenium-186 and rhenium-188 as radioactive isotopes in diagnostic and therapeutic applications are increased very much due to the characteristic radiochemical and chemical properties of these two radioisotopes. In particular, chemical similarities between99Tc and99mTc pair and186Re and188Re pair make it easier to correlate the two groups of compounds. Rhenium-188 is generated from the beta-decay of tungsten-188 which was produced by double neutron capture on enriched tungsten-186 oxide. It is of great interest to examine the impurities in the eluate by radiochemical neutron activation. For this purpose, the preconcentration of the impurities in samples were necessary, and it was achieved by adsorption on hydrated magnesium oxide.

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Abstract

The thermo-programmed reduction study of Pt/WOx–ZrO2 materials prepared with different tungsten loading were performed by thermogravimetry. The samples were synthesized by impregnation method and calcined at 600, 700 and 800°C. The characterizations of both un-calcined and calcined materials were carried out using different techniques: thermal analysis (TG and DTA), X-ray diffraction (XRD) and thermo-programmed reduction (TPR). TG and DTA analysis of un-calcined were used to determination of calcination temperatures of the samples. XRD diffractograms were useful to help us in the determination of phase presents. TPR profiles showed between three and four events at different temperatures attributed to platinum reduction and the different stages of tungsten specie reduction.

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Abstract  

Two improved processes of99Mo production have been developed on laboratory scale. The first one allows to purify Mo of natural isotopic composition from tungsten impurities from 64 to <10 ppm by using preferential adsorption of tungsten on hydrated tin(IV) oxide (SnO2 nH2O) before irradiation in a nuclear reactor. The second process deals with the separation of pure fission product99Mo from235U irradiated in a reactor. Two versions of separation process for production of fission99Mo have been developed. Both versions start with the dissolution of235U oxide target in nitric acid and are based on sequential use of alumina and anion exchange resin AG® 1-X8 columns. The yield of99Mo in both versions is 80–89%.

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Abstract  

The chemical aspects of isotopic fractionation in a multiple filament thermal ionization source were investigated. Samples of uranium were loaded as nitrates, chlorides and sulphates. The dependence of measured isotopic ratios on the filament material and the chemical form of the loading solution was studied. The dependence of the formation of uranium and its oxide ions on various chemical and instrumental conditions were investigated using tungsten and rhenium filaments.

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Journal of Radioanalytical and Nuclear Chemistry
Authors: I. Kikoin, S. Yakimov, N. Chernoplekov, V. Petrenko, K. Balashov, A. Knyazyatov, V. Gerasimov, V. Zenkevich, N. Tarasov, A. Malinin, M. Kozlova, V. Kharlamov, and N. Kurenkov

Abstract  

Highly enriched xenon124Xe /99.85%/ has been used for the experimental production of iodine123I by the /,n/ reaction. As the radiation source served a 30–45 MeV electron beam produced by a linear accelerator and converted by a tungsten converter to -radiation. The yield and radionuclidic purity of123I have been estimated, the content of isotopic impurities /124I and125I/ being for 30 MeV irradiations lower than 4×10–3%/.

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