Abstract: A large enhancement of neutron flux is realized when a primary target of D2O and H2O is contained in a vessel, is irradiated by an electron beam incident on a gamma converter and where the vessel is enclosed within a neutron reflector material including Nickel and Polyethylene. A very large enhancement of neutron flux is realized when a secondary target of LEU is mixed with the primary target resulting in a very large enhanced production of Molybdenum-99. The primary target and the secondary target is contained in cylindrical or spherical vessels. A process for extracting produced Mo-99 from the reaction vessel solution.

Abstract: Methods and apparatus for separating ions of metallic elements are provided. Preferred methods utilize a hydrophobic chelating extractant, such as an organophosphorus compound, adsorbed onto carbon or graphite fibers in the form of felt. Also described is a new thallium-201 generator that comprises a column containing an acidic organophosphorus extractant adsorbed on carbon or graphite fibers, and a yttrium-90 generator system comprised of two extraction columns designed to selectively absorb yttrium-90 at different pH, to enable the separation of yttrium-90 from strontium-90. The two columns are connected in series for stepwise separation. The yttrium-90 product is freed from residual strontium-90 and metal contaminants and can be eluted from the second column with dilute acid, acetate buffer, water or saline for labeling biological targeted molecules. The new generator system provides rapid and efficient separation of yttrium-90 and is amenable to both scale-up and automation.

Abstract: Methods and apparatus for separating ions of metallic elements are provided. Preferred methods utilize a hydrophobic chelating extractant, such as an organophosphorus compound, adsorbed onto carbon or graphite fibers in the form of felt. Also described is a new thallium-201 generator that comprises a column containing an acidic organophosphorus extractant adsorbed on carbon or graphite fibers, and a yttrium-90 generator system comprised of two extraction columns designed to selectively absorb yttrium-90 at different pH, to enable the separation of yttrium-90 from strontium-90. The two columns are connected in series for stepwise separation. The yttrium-90 product is freed from residual strontium-90 and metal contaminants and can be eluted from the second column with dilute acid, acetate buffer, water or saline for labeling biological targeted molecules. The new generator system provides rapid and efficient separation of yttrium-90 and is amenable to both scale-up and automation.

Abstract: Methods and apparatus for separating ions of metallic elements are provided. Preferred methods utilize a hydrophobic chelating extractant, such as an organophosphorus compound, adsorbed onto carbon or graphite fibers in the form of felt. Also described is a new thallium-201 generator that comprises a column containing an acidic organophosphorus extractant adsorbed on carbon or graphite fibers, and a yttrium-90 generator system comprised of two extraction columns designed to selectively absorb yttrium-90 at different pH, to enable the separation of yttrium-90 from strontium-90. The two columns are connected in series for stepwise separation. The yttrium-90 product is freed from residual strontium-90 and metal contaminants and can be eluted from the second column with dilute acid, acetate buffer, water or saline for labeling biological targeted molecules. The new generator system provides rapid and efficient separation of yttrium-90 and is amenable to both scale-up and automation.

Abstract: Methods, compounds, compositions and kits that relate to pretargeted delivery of diagnostic and therapeutic agents are disclosed. In particular, methods for radiometal labeling of biotin, as well as related compounds, are described. Articles of manufacture useful in pretargeting methods are also discussed.

Abstract: Stable therapeutic radionuclide compositions comprising, for example, .sup.186 Re, .sup.188 Re and .sup.131 I stably bound to a proteinaceous targeting moiety and suitable for human in vivo administration are disclosed. Stabilizing agents preferably comprise antioxidants and challenging agents, and combination of HSA with an antioxidant and/or challenging agent provides enhanced long term stability. Ascorbic acid is an especially preferred stabilizing agent, which provides stability of therapeutic radionuclide compositions at levels of at least about 90% for several hours up to several days.

Abstract: Stable therapeutic radionuclide compositions comprising, for example, .sup.186 Re, .sup.188 Re and .sup.131 I stably bound to a proteinaceous targeting moiety and suitable for human in vivo administration are disclosed. Stabilizing agents preferably comprise antioxidants and challenging agents, and combination of HSA with an antioxidant and/or challenging agent provides enhanced long term stability. Ascorbic acid is an especially preferred stabilizing agent, which provides stability of therapeutic radionuclide compositions at levels of at least about 90% for several hours up to several days.

Abstract: Water soluble irradiation targets are disclosed for the production of .sup.186 Re and .sup.188 Re. The irradiation targets are selected for both water solubility and absence of elements which would produce contaminating isotopes for medical therapeutic and diagnostic use. In one embodiment, .sup.186 Re or 188Re is produced by the direct irradiation of a water soluble irradiation target comprising .sup.185 Re or .sup.187 Re, respectively. Preferred targets for this purpose include aluminum perrhenate, lithium perrhenate and magnesium perrhenate. In another embodiment, a zirconyl tungstate generator comprising .sup.188 W for the production of .sup.188 Re is obtained by irradiating a soluble irradiation target comprising .sup.186 W, dissolving the irradiated target in aqueous solution, reacting the dissolved target with an aqueous solution comprising zirconyl ion to form an insoluble zirconium tungstate precipitate and disposing the precipitate in an elutable container.

Abstract: Water soluble irradiation targets are disclosed for the production of .sup.186 Re and .sup.188 Re. The irradiation targets are selected for both water solubility and absence of elements which would produce contaminating isotopes for medical therapeutic and diagnostic use. In one embodiment, .sup.186 Re or .sup.188 Re is produced by the direct irradiation of a water soluble irradiation target comprising .sup.185 Re or .sup.187 Re, respectively. Preferred targets for this purpose include aluminum perrhenate, lithium perrhenate and magnesium perrhenate. In another embodiment, a zirconyl tungstate generator comprising .sup.188 W for the production of .sup.186 Re is obtained by irradiating a soluble irradiation target comprising .sup.186 W, dissolving the irradiated target in aqueous solution, reacting the dissolved target with an aqueous solution comprising zirconyl ion to form an insoluble zirconium tungstate precipitate and disposing the precipitate in an elutable container.

Abstract: Improved radionuclide generators include a substantially insoluble salt of a parent radionuclide precursor which may be directly irradiated and then packed in a column for subsequent elution of the daughter radionuclide without the production of counter ion isotopic contaminants. The parent radionuclide precursor is provided in the form of an insoluble salt of the parent element whose counter ion, preferably aluminum, forms a relatively soluble salt with the desired daughter radionuclide. The improved generators may be prepared by reacting a parent radionuclide precursor with aluminum to obtain an aluminum salt of the precursor having low solubility in water, irradiating the aluminum salt to obtain an irradiated aluminum salt of the parent radionuclide, and then disposing the irradiated parent radionuclide in an elutable container. Useful parent radionuclide precursors include molybdenum-98 in the form of molybdate for the production of daughter .sup.