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The thermodynamics of extraction equilibria

III. The uranyl chloride—hydrochloric acid—Di-2-ethylhexyl phosphoric acid—Toluene system

Journal of Radioanalytical and Nuclear Chemistry
Authors: A. Ruvarac, Z. Maksimović, and R. Halaši

Abstract  

A simple graphical method for determination of thermodynamic equilibrium constants, developed for ion-exchange and solvent extraction processes, was successfully applied to a liquid exchangersystem. Close values of the thermodynamic equilibrium constants for the system uranyl chloride—hydrochloric acid—di-2-ethylhyxyl phosphoric acid—toluene (K=7.8±0.8) were obtained when the ionic strength of the aqueous phase was varied and the concentration of di-2-ethylhexyl phosphoric acid in the organic phase was kept constant, and vice versa.

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Determination of the balance of the nuclear reactor fuel burn-out process by gamma-spectrometry of fission products III

Determination of the burn-up on the basis of the activity quotients106Ru/137Cs and134Cs/137Cs

Journal of Radioanalytical and Nuclear Chemistry
Authors: V. Bulovič, J. Krtil, F. Sus, Z. Maksimovic, and E. Klosova

Abstract  

The possibility for the determination of heavy water reactor fuel burn-up on the basis of gamma-spectrometric measurements of the activity quotients106Ru/137Cs and134Cs/137Cs has been experimentally investigated. The investigation has been carried out on the non-enriched uranium metal fuel of the Czechoslovak Nuclear Power Plant Al. A spectrometer with germanium detector has been used for spectrum analysis of the irradiated fuel gamm-radiation. Burn-up has been determined (1) by the applied here procedure, and (2) from the results of mass-spectrometric determination of the isotopic composition and content of U, Pu and Nd. Two groups of the values obtained have been compared and the influence of the errors of the measured activity quotients on the established deviations has been evaluated.

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Abstract  

Solvent extraction of 3,5-dinitrosalicylic (3,5-DNS) and 2-oxy-5-nitropyridinic (2-O-5-N-Py) acids and their Ni(II), Co(II) and Cu(II) complexes from sulphuric acid medium with TBP and TOPO in n-hexane was investigated. The compositions of the extractable species were determined by slope analysis. Possible utilization in separation processes is discussed in general.

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Abstract  

Determination of106Ru,134Cs,137Cs and144Ce in samples of irradiated fuel from the Czechoslovak atomic power station Al is described. The determination is based on gamma-spectrum analysis. The analysis was performed using a Ge(Li) semiconductor detector; for the determination of the isotope mentioned the lines in the energy interval from 400 to 1300 keV were used. The analyses of both dissolved and non-dissolved samples of the fuel were performed. The results of the determinations and their comparison are given in detail.

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Abstract  

Determination of the isotopic composition and concentration of uranium, plutonium and neodymium by mass-spectrometric isotope dilution is described. Isotopes233U,242Pu and150Nd were used as spikes. Isotopic composition was measured with a Varian-TH 5 mass spectrometer. Optimum amounts loaded onto the filament were 2–5 μg U, ∼0.1 μg Pu and <0.1 μg Nd. The accuracy and reproducibility of the isotopic ratio and concentration measurements were evaluated.

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Abstract  

Individual steps of the neodynium method for burn up determination are discussed. The main attention is paid to neodymium separation from fission products, mass-spectrometric measurement of its isotopic composition, and to the calculation of the burn up results from the measured data. The conclusions were verified on burn up analysis for the irradiated fuel from heavy and light water reactors.

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