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The radiation resistance of sorbents AG 50 W-X8, Ac resin, and UTEVA resin in contact with hydrochloric solutions under irradiation with 10 MeV electrons in a wide absorbed-dose range up to 2 MGy was studied. Mass distribution ratios and total sorption capacity were used as quantitative measures to determine the changes in ion exchange or extractive abilities of the resins. Based on the data obtained and on a review of the performance of the 225Ac/213Bi generators reported in the literature, the applicability of investigated resins for high activity loaded onto different generator systems was concluded. [ABSTRACT FROM AUTHOR]

Scheme of a two-column 225Ac/213Bi generator using inorganic sorbents based on hydrated titanium oxide (JSC "Termoxid") and hydrated zirconium oxide modified with nickel-potassium ferrocyanide (Termoxid, T-35) is suggested. 213Bi is obtained via a prolonged washing-out of 221Fr from the first column with T-5 sorbent containing 225Ac and its retention in the second column with T-35 for the decay and accumulation of 213Bi, which is extracted afterwards with a 1 M HCl solution. The direct-flow and circulatory schemes were tested, and the properties of the generator toward radionuclides of the 225Ac subfamily were determined in a wide range of flow rates and eluent volumes. It is assumed that the sorbents of the T-5 and T-35 brands are suitable for creating a 225Ac/213Bi generator with activity of hundreds of 225Ac mCi. [ABSTRACT FROM AUTHOR]

A scheme of an "inverse" generator based on an inorganic sorbent (annealed zirconium and yttrium mixture oxides) has been proposed and tested. The generator demonstrated high yield of the 213Bi product (up to 97 % in 0.5 mL of eluate), high degree of purification from the actinium isotopes (up to 10−2 % of initial 225Ac in 3 M NaNO3 solution), as well as the products of 227Ac decay, and low radiation impact on the sorbent. Application of circulating approach to the sorption of 213Bi provides decreasing processing time to 5 min at higher yield of the product. [ABSTRACT FROM AUTHOR]

The ability of inorganic hydroxide sorbents Termoxid-5 (T-5) and Termoxid-39 (T-39) heat-treated at temperatures from 100 to 950°C to take up radionuclides of the 225Ac subfamily was examined in a wide range of solution acidities and salt compositions. T-5 and T-39 are principally suitable for the development of both direct and inverse 225Ac/213Bi generators with the activity of hundreds of millicuries of 225Ac. [ABSTRACT FROM AUTHOR]