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Hydrogen titanate nanotubes (H2Ti3O7) were synthesized by hydrothermal process using 10 M NaOH and TiO2 anatase powder. The material synthesized was characterized by powdered X-ray diffraction (XRD), scanning electron microscopy (SEM) and transmission electron microscopy (TEM) to ensure the structural and morphological details of the above said nanotubes. This nanosized material behaved as a cation exchanger and it was employed to separate carrier-free 137mBa from 137Cs in column chromatographic technique using 1.0 M HNO3 as eluting agent.

Solvent extraction behavior of carrier-free Mo and W from 0.1–11 M HCl into 0.05 M Aliquat 336-chloroform solution was investigated and compared with that of macro amounts of Mo and W. The distribution ratios of carrier-free Mo and W were in good agreement with those of macro amounts of Mo and W in 6–11 M HCl, while the extraction efficiencies of carrier-free Mo and W were different from those of macro amounts of Mo and W in

A device for on-line electromigration studies of radio-elements in free electrolytes has been tested by measuring the absolute individual ion mobilities of no-carrier-added single charged anions [99mTc]TcO4 - and [18F]F- and differently charged cations [137Cs]Cs+, [57Co]Co2+ and [241Am]Am3+ in inert aqueous electrolytes at 298.1 K. The observed ion mobilities were found to be influenced by electroosmosis in the migration tube. A relation to correct this effect is proposed. In addition, it was shown that the effect of electroosmosis may be suppressed by chemical treatment of the surface of the migration tube.

The potential associated with the electrochemical deposition of radionuclides in metallic form from solutions of extremely small concentration is strongly influenced by the choice of the electrode material. In a macroscopic model, the interaction between the microcomponent and the electrode material is described by the partial molar adsorption enthalpy and -entropy. By combination with the thermodynamic description of the electrode process, a potential is calculated that characterizes the process at 50% deposition. Model calculations for Ni-, Cu-, Pd-, Ag-, Pt-, and Au-electrodes and the microcomponents Hg, Tl, Pb, Bi, and Po confirm the decisive influence of the electrode material on the deposition potential. The present study prepares an application of the same model to the superheavy elements 112-116.

Heavy ion activation of natural Sb2O3 with 78 MeV 16O6+ results in the formation of carrier-free praseodymium isotopes, 133,135Pr, and their corresponding decay products 133,135Ce, in the matrix. Also irradiation with ~ 90 MeV 19F7+ beam leads to the production of carrier-free neodymium isotopes, 135-138Nd, which decay out to 135-138Ce via 135-138Pr. Another way for the production of carrier-free 135Ce radionuclide is to irradiate CsNO3 target with 7Li3+ beam of energy 44 MeV. The shorter lived radionuclides of cerium decay out and a radiochemical procedure has been developed for the separation of carrier-free radionuclides from the bulk target matrix antimony and caesium through liquid-liquid extraction (LLX) using Aliquat 336 (tricaprylmethylammonium chloride), and di-(2-ethylhexyl)phosphoric acid (HDEHP) as extractants.

Summary Reactor Irradiation of natural osmium leads to osmium-194 by second order neutron capture. When converted to osmium tetroxide, millicurie amounts of carrier-free iridium-194 can be recovered repeatedly from the decay of a Single sample of osmium-194 by vacuum distillation. The half-life of pure iridium-194 was found to be 17.4 ± 0.1 hours.

Summary A simple procedure is described for the preparation of pure 228Ac (MsTh2) from 228Ra(MsTh1). After initial purification of 228Ra from 228Th, the sample is left for a month 228Ra for and its daughters to decay completely. After this period, the Separation of 228Ac is straightforward. Using Dowex 50X8 resin and dilute nitric acid as eluting Solution, 228Ac is obtained in high specific activity and in carrier free form in a reasonably Short time. Rapid milking of 228Ac can be achieved daily by the use of 0,5 M ammonium-glycolic or an ammonium-α-hydroxyisobutyric solutions of p H about 4.