Separation of ²³⁰Th (Ionium) from Uranium Ores in Sulfuric Acid and in Nitric Acid Solutions

Abstract

230 Th (ionium) is of interest for production of 23 'Pa, the Pa isotope with the longest half life, and for production of 232 U which can be used in radionuclide batteries. Two procedures are presented which have been worked out for separation of 23^T h from sulfuric acid and from nitric acid solutions. In the first case the effluents from the anion exchange resins are the starting material for recovery of 230 Th, in the second case the cation exchange resins which are used for purification of U. The procedures selected are simple, economic and can be performed in any uranium mill or uranium purification plant without additional investments.

Separation of Thorium, Protactinium and Uranium by Ion Exchange and Extraction

“…(3) 230 Th can be isolated in the course of the procedures of uranium recovery [1 ]. Its separation is much easier than the isolation of protactinium from the residues of uranium recovery.…”