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- Author or Editor: J. Gascón x
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Abstract
In radiochemical analysis, the storage of a tracer solution is an important issue to bear in mind. The evaporation of the tracer solution depends on the type of container used for storing. In this paper the evaporation rate in four kinds of containers, i.e., flame-sealed glass ampoule, sealed glass flask, flame-sealed polyethylene ampoule and screw glass vial was studied. It is concluded that the evaporation rate depends on the system of closing.
Abstract
In radiochemical analysis, specially by using high resolution alpha-spectrometry, a key issue is the determination of the radiochemical yield. Radiochemical yield allows to determine the concentration of the radionuclide of interest and the quality of the chemical separation. To determine the radiochemical yield it is necessary to know the solid state detector efficiency, which can be obtained by calibration with a circular calibrated source. In this paper the optimization of the parameters affecting both the calibration and measurement of a source by alpha-spectrometry is described. The optimization is based on two sets of data: experimental and theoretical. Experimental data were obtained from the calibration of the solid state detector with four calibrated 241Am sources. Theoretical data were calculated by geometry formulas and were verified experimentally.
Abstract
In this paper the authors present a study of the adsorption of thorium on manganese dioxide by batch equilibration and cartridge experiments. Some anomalies in the use of MnO2 to concentrate thorium have been found. So the use of this technique is limited for the determination of thorium in natural waters.
Abstract
Adsorption of americium with manganese-dioxide-impregnated filters has been studied. The adsorption of americium decreases as the pH increases due to its hydrolysis. From the reported laboratory experiments, it can be concluded that the adsorption on manganese-dioxide filters is not a reliable method to determine americium in natural waters.
Abstract
The determination of Am and Cm in typical waste streams from nuclear power plants using anion exchange chromatography has some drawbacks like the contamination by Pu and Po. This improved procedure solves these problems, and it has been applied with success to the analysis of Am and Cm in nuclear waste samples: ion exchange resins, ion exchange resins solidified with cement and evaporator concentrates.