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  • Author or Editor: J. Janczyszyn x
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Abstract  

The method of simulation of gamma-spectra based on the experimental library spectra of particular radioisotopes is described. The library spectra were obtained by activation of pure element sample with the use of a 14 MeV neutron generator, counting them with a NaI(T1) scintillation spectrometer and decomposing of mixed spectra to spectra of separate radioisotopes. The simulated and measured spectra of an artificial sample are compared.

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Abstract  

The possibility of the use of characteristic X-rays, emitted after IT of EC type of radioactive decay, for analytical purposes in 14 MeV neutron activation analysis was investigated. Elements from Cr to U were theoretically considered and 24 of them experimentally examined. The results showed usefulness of the technique for several elements in spite of the troublesome selfabsorption effect. It is expected that the 0.1% determination limit can be achieved for the most suitable elements.

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Abstract  

The cross-sections for the production of the short-lived nuclides:26mAl,197mAu,136mBa,79mBr,139mCe,34Cl,167mEr,114m3In,114m2In,38mK,38mCl,26Na,20F,192Re,207mPb,203mPb,46mSc,183mW,90mZr obtained from (n, 2n), (n, n′), (n, alpha), (n,p) reactions using 14 MeV neutrons, were evaluated by the activation method. The experimental results of this work were compared with those obtained by other authors.

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Abstract  

Mathematical considerations on the optimization of the flow and mechanical parameters of a system for continuous analysis of liquids are presented. The system in question contains a pump, an activation vessel placed in the vicinity of a neutron generator target, a pipeline and a vessel for the measurement of the induced activity. The following parameters of the system were taken into consideration: volumes of the activation and measurement vessels, position of the activation vessel with respect to the neutron generator target, shape of the activation vessel, and flow rate of the pumped fluid. The system is adapted for continuous and interrupted mode of operation of the neutron generator. The results of the theoretical considerations were verified in practice with the use of the above system and the reaction16O (n, p)16N. The agreement of theory and experiment was proved.

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Abstract  

A system of programs performing calculations for relative instrumental neutron activation analysis with germanium detectors was developed. It can be used if standards and unknowns are irradiated together and measured at the same counting geometry. Experimental and library data are evaluated by five programs. The final result is a table of concentrations. The whole system works automatically, without the intervention of an operator and runs on an IBM-PC.

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Abstract  

Analysis of steel for aluminium, silicon and oxygen is presented. The use of a Ge(Li) detector and the technique of precise photopeak integration enabled to attain a detection limit of 0.04% for Al. A method of the evaluation of the iron interference in silicon determinations is proposed.

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Abstract  

The method of non-destructive analysis for Al, Si and O in non-metallic inclusions isolated from steel is presented. The small powdered samples varying in mass from 2 mg to 40 mg were analysed, thus making the development of a proper technique of sample preparation necessary. The specific activation geometry and rotation of samples during irradiation were chosen to improve the accuracy and precision. Lower limits of determination for Al, Si, and O were: 1.4 mg, 0.3 mg, and 0.8 mg, respectively.

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