Abstract: Inert gaseous fission products, including beryllium, rubidium, and krypton isotopes, resulting from the operation of a uranyl sulfate water solution nuclear reactor are passed through a delaying device to precipitate out strontium-90, then passed to a second delaying device to precipitate out the desired strontium-89.

Abstract: A high radiation resistant inorganic sorbent is used for the extraction of Mo-99 from the fission byproducts of a uranyl sulfate nuclear-fueled homogeneous-solution nuclear reactor. The sorbent is a composition of hydrated titanium dioxide combined with 5 to 40 mole percent zirconium hydroxide formed into pellets and saturated with an isotope composition of uranium.

Abstract: The electric mammograph is an electrical impedance tomograph device for obtaining three-dimensional images of the conductivity distribution in biological tissues. A planar array of electrodes is put in contact with the tissues of interest. An AC source is connected to a single remotely attached electrode and to one of the planar array electrodes. Potential differences between the at rest electrodes in the planar array and a second remote at rest electrode are measured. The images are reconstructed using a modified back projection method.

Abstract: A beam of accelerated charged particles irradiates an arsenide target, such as gallium arsenide or aluminum arsenide, to produce radioisotopes of selenium and other radionuclides. The irradiated target is placed in a niobium, tantalum, or graphite vessel and inserted into a tube. Metallic reagents consisting of an alloy of iron, nickel, and chromium (stainless steel) or metallic aluminum are mixed with the target material. The target is then heated to 1000-1100.degree. C. The metallic reagents prevent arsenic sublimation, destroy the crystalline structure of arsenide target, and remove other impurities, such as zinc-65. The target is then heated a second time to about 1300.degree. C. causing the selenium-72 to sublime and be deposited on a cooler wall of the tube or on a catcher foil surface. The deposited selenium-72 is recovered from the tube or foil.

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.