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.
Authors:V. Bulovič, J. Krtil, F. Sus, Z. Maksimovic, and E. Klosova
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
Authors:Z. Maksimović, D. Misković, M. Kopečni, J. Živanov, and R. Halaši
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.
Authors:V. Bulovič, J. Krtil, F. Sus, Z. Maksimovič, and E. Klosová
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.
Authors:F. Sus, J. Krtil, V. Bulovič, E. Klosová, and Z. Maksimovič
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.
Authors:J. Krtil, F. Sus, V. Bulovič, E. Klosová, and Z. Maksimovič
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.