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Abstract  

The effects of acids on the removal of impurity from 2N grade silica have been studied using five leaching acids: 0.2 M-oxalic acid (pH 1.5 and 2.5), c-aqua regia, 2.5%—HCl/HF, and 1%—HNO3/HF. The presence of 39 impurities in the 2N grade silica and the reference material (RM, 5N grade silica) were investigated by neutron activation analysis (NAA), X-ray fluorescence (XRF), and inductively coupled plasma mass spectrometry (ICP-MS) methods. Major impurities of the 2N silica were Al, K, Fe, Na, Ti, Ca, Mg and P. The fractions of the eight major impurities were 99.2% and 90.9% of total impurity in the 2N and RM silica, respectively. Among the leaching acids, almost all of the major impurities were removed effectively by the 2.5% HCl/HF leaching acid. All the major impurities, except for phosphorous, as well as 21 minor and trace impurities could be determined by the NAA.

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Journal of Radioanalytical and Nuclear Chemistry
Authors: A. Berlizov, I. Malyuk, A. Sajeniouk, V. Tryshyn, V. Petrov, A. Savin, S. Abousahl, G. Rasmussen, I. Sadikov, and F. Tashimova

Abstract  

A gamma-spectrometric and radiochemical analysis was carried out of a material (Zr-2.5% Nb alloy) of technological channels (TC) of Chernobyl Nuclear Power Plant (NPP) power unit No. 2 RBMK-1000 reactor, being under the beginning stage of decommissioning. Activities of 90Sr, 137Cs, 238Pu, 239+240Pu, 241Am and 244Cm were determined. It was established that the main source of the revealed actinides and fission products was an impurity of natural thorium and uranium in TC source material on the level of several tenths of ppm. Impurity analysis of TC source material was performed by neutron activation analysis (NAA) and inductively coupled plasma mass spectrometry (ICP-MS). Fission product and transuranium element activities measured were compared with the results of prognostic calculations performed with the help of the NAAPRO code.

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Abstract  

Trace metallic impurity analysis by spectroscopic techniques is one of the important steps of chemical quality control of nuclear fuel materials. Depending on the burn-up and the storage time of the fuel, there is an accumulation of 241Am in plutonium based fuel materials due to β decay of 241Pu. In this paper, attempts were made to develop a method for separation of 241Am from 1.2 kg of analytical solid waste containing 70% U, 23% Pu, 5% Ag and 1–2% C as major constituents along with other minor constituents generated during trace metal assay of plutonium based fuel samples by d. c. arc carrier distillation atomic emission spectrometry. A combination of ion exchange, solvent extraction and precipitation methods were carried out to separate ~45 mg of 241Am as Am(NO3)3 from 15 L of the analytical waste solution. Dowex 1×4 ion exchange chromatographic method was used for separation of Pu whereas 30% TBP–kerosene was utilized for separation of U. Am was separated from other impurities by fluoride precipitation followed by conversion to nitrate. The recovery of Pu from ion exchange chromatographic separation step was ~93% while the cumulative recovery of Am after separation process was found to be ~90%.

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system suitability parameters like retention times, peak resolution, theoretical plates and tailing factor of all the known impurities are calculated through the Labsolution software ( Table 5 ). The impurity analysis of marketed samples of both sodium

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ingredients, < 10% for related compounds) [ 22 ]. Conclusion This study presents a detailed step-by-step development of a new HILIC method for amlodipine besylate and its specific impurities analysis, using a chemometric approach. Using response surface

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