Abstract: A polymer sorbent for the extraction of Mo-99 from the fission byproducts of a uranyl sulfate nuclear-fueled homogeneous-solution nuclear reactor and the method of producing the sorbent are described. This sorbent is produced from a maleic anhydride copolymer and .alpha.-benzoin-oxime. The sorbent is produced by reacting a mixture of maleic anhydride copolymer, a bifunctional organic compound (hydrochinon, diethyleneglycol, hexamethylene diamine, glycerol, ethyleneglycol), and .alpha.-benzoin-oxime in the ratio of 1:(0.25-0.50):(0.75-0.5) in a polar organic solvent (dioxane, dimethyl formamide, or toluene) in the temperature range of 90.degree.-95.degree. C. with constant stirring for 1 to 2 hours. The resultant product is then cooled to room temperature and flushed 3-5 times with cold water. A white stringy product results. This is dried and crushed. Particles of 1-2 mm in diameter are selected for the solid sorbent.

Abstract: The current invention involves a means for the production and extraction of the isotope molybdenum-99 for medical purposes in a waste free, simple, and economical process. Mo-99 is generated in the uranyl sulphate nuclear fuel of a homogeneous solution nuclear reactor and extracted from the fuel by a solid polymer sorbent with a greater than 90% purity. The sorbent is composed of a composite ether of a maleic anhydride copolymer and .alpha.-benzoin-oxime.