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- Author or Editor: B. Bartoś x
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Abstract
The distribution coefficients of Cd2+ and In3+ on crystalline antimonic(V) acid (C-AA) have been determined in order to find the best conditions for separation of both cations. Very high affinity of C-AA for Cd2+ ions enables to separate115mIn from115Cd in a single-step rapid procedure. The indium fraction obtained was very pure; the amount of radioactive contaminants was less than 0.0005%.
Abstract
Properties and applications of composite ion exchangers developed in this Institute are described. The new sorbents consist of a selective inorganic ion exchanger, e.g., hexacyanoferrate of transition metals or hydrated antimony pentoxide, firmly incorporated into a resin matrix, e.g., phenol-formaldehyde, of various shapes. The composites have proved to be effective adsorbents for radionuclides of cesium, sodium, francium, elements 104 and 105, and some others. The sorbents were successfully tested as filter fillers for radiocesium removal from liquid radioactive wastes and from other solutions encountered in nuclear technology. They were also applied in radiochemical studies and in nuclear activation analysis.
Abstract
An effective and simple process for the separation of 177Lu from neutron-irradiated Yb targets was developed. Irradiated Yb target was dissolved in H2SO4 solution and after reduction with sodium amalgam Yb was precipitated in the form of YbSO4. From 50 mg of Yb irradiated target only 1 mg Yb remains in solution after precipitation and separation of YbSO4. The overall recovery of 177Lu is estimated at 73%. Further efficient chromatographic separation of carrier-free 177Lu from 1 mg of Yb is relatively easy and is described in several papers.
Summary
82Rb is a generator produced positron-emitting isotope (T 1/2 = 75 s) that is increasingly being used in positron emission tomography for the characterization of myocardial perfusion. The parent radionuclide of 82Rb, strontium 82Sr, is produced mainly by a (p, 4n) reaction induced by >40 MeV protons on rubidium (85Rb) target. In the present work we propose a new fast and simple procedure for 82Sr separation from the target, based on selective adsorption of rubidium on the inorganic ion-exchanger: cryptomelane MnO2.
Abstract
Recent work directed towards synthesizing and exploring new effective sorbents for radiocesium removal from primary coolants of pressurized water nuclear reactors of the WWER type is presented. Various sorbents synthesized on the basis of titanium hexacyanoferrate are compared with one another from the point of view of their sorption efficiency and stability. The uptake of137Cs from solutions containing boric acid and millimolar quantities of ammonium and potassium ions was studied under conditions simulating the process of purification of the coolant bled from the primary circuit of the reactor. A composite-type sorbent was selected of good mechanical properties and negligible solubility, efficiently decontamining large amounts of the solution (considerably exceeding 104 bed volumes) in the course of the column process.
Abstract
103mRh is a very promising radionuclide for Auger electron therapy due to its very low photon/electron ratio. The goal of the present work was the elaboration a method for production of large quantities of 103mRh for generator system. It was found that the combination of solvent extraction with evaporation of 103RuO4 followed by decomposition of H5IO6 makes it possible to produce 103mRh of high radionuclidic and chemical purity.
Abstract
Zinc and nickel hexacyanoferrates (II) present a high affinity for223Fr and no retention for223Ra in hydrochloric acid solutions with concentrations greater than 0.5N. Hydrated antimony pentoxide is the best sorbent for223Ra. Incorporated in a composite exchanger, it could be used for decontamination purposes.
Abstract
A composite ion exchanger containing hydrated antimony pentoxide (HAP) in polystyrene-divinylbenzene matrix has been prepared. Its sorption properties with respect to Na, As, Au, Cd, Cu, Ga, Hg, In, K, La, Mn, Mo (Tc), Pd, Pt, Sb, W and Zn have been examined. Sodium is quantitatively retained on the sorbent from 8M HCl solution as well as from a mixture of conc. H2SO4+ conc. HNO3+H2O (1+1+2). As, W, Cd and Sb are partially retained, while the remaining elements are not retained and can be quantitatively eluted. The composite ion exchanger is stable to oxidizing acid media and it can be directly applied to separation of24Na from mineralizates of neutron-irradiated biological materials.
