Abstract: A Molybdenum/Technetium 99-m generator containing a metal-molybdate containing powder and an alumina sorbent. A preferred alumina sorbent is a gamma-phase alumina (?-Al2O3), a chi-phase alumina (?-Al2O3), or a combination thereof.

Abstract: A method of inspecting a material includes examining a surface of a test material with an eddy current sensor and applying an X-ray fluorescence analysis to the surface of the test material at the same location at which the eddy current examination was performed.

Abstract: A method of making Lu-177 involving dissolving enriched Yb2O3, loading dissolved enriched Yb2O3 on a first guard column containing resin prepared from (2-ethyl-1-hexyl)phosphonic acid mono(2-ethyl-1-hexyl)ester (HEH[EHP]), passing a first separation of a stream exiting from first guard column through a first resin cartridge containing dipentyl pentylphosphonate, collecting Lu-177 onto a first collection column having resin containing tetraoctyl diglycolamide (DGA), loading an exiting stream from first collection column on a second guard column containing resin prepared from (2-ethyl-1-hexyl)phosphonic acid mono(2-ethyl-1-hexyl)ester (HEH[EHP]); passing a first separation of a stream exiting from second guard column through a second resin cartridge containing dipentyl pentylphosphonate; collecting Lu-177 onto a second collection column having resin containing DGA; passing a second separation of a stream exiting from second guard column through a third resin cartridge containing dipentyl pentylphosphonate; and

Abstract: A method of inspecting a material includes examining a surface of a test material with an eddy current sensor and applying an X-ray fluorescence analysis to the surface of the test material at the same location at which the eddy current examination was performed.

Abstract: A process for producing a metal-molybdate material is provided. The process includes a step of reacting a metal molybdenum (Mo) material in a liquid medium with a first acid to provide a Mo composition and combining the Mo composition with a metal source to provide a metal-Mo composition. The metal-Mo composition can be pH adjusted with a base to precipitate a plurality of metal-Mo particulates.

Abstract: A process for producing a metal-molybdate material is provided. The process includes a step of reacting a metal molybdenum (Mo) material in a liquid medium with a first acid to provide a Mo composition and combining the Mo composition with a metal source to provide a metal-Mo composition. The metal-Mo composition can be pH adjusted with a base to precipitate a plurality of metal-Mo particulates.

Abstract: A process for producing a metal-molybdate material is provided. The process includes a step of reacting a metal molybdenum (Mo) material in a liquid medium with a first acid to provide a Mo composition and combining the Mo composition with a metal source to provide a metal-Mo composition. The metal-Mo composition can be pH adjusted with a base to precipitate a plurality of metal-Mo particulates.

Abstract: A process for producing a titanium-molybdate material is provided. The process includes a step of reacting a metal molybdenum (Mo) material in a liquid medium with a first acid to provide a Mo composition and combining the Mo composition with a titanium source to provide a Ti—Mo composition. The Ti—Mo composition can be pH adjusted with a base to precipitate a plurality of Ti—Mo particulates.

Abstract: A process for producing a titanium-molybdate material is provided. The process includes a step of reacting a metal molybdenum (Mo) material in a liquid medium with a first acid to provide a Mo composition and combining the Mo composition with a titanium source to provide a Ti—Mo composition. The Ti—Mo composition can be pH adjusted with a base to precipitate a plurality of Ti—Mo particulates.

Abstract: A process for producing a metal-molybdate material is provided. The process includes a step of reacting a metal molybdenum (Mo) material in a liquid medium with a first acid to provide a Mo composition and combining the Mo composition with a metal source to provide a metal-Mo composition. The metal-Mo composition can be pH adjusted with a base to precipitate a plurality of metal-Mo particulates.

Abstract: The present invention relates generally to the field of gamma ray spectroscopy monitoring and a system for accomplishing same to monitor one or more aspects of various isotope production processes. In one embodiment, the present invention relates to a monitoring system, and method of utilizing same, for monitoring one or more aspects of an isotope production process where the monitoring system comprises: (A) at least one sample cell; (B) at least one measuring port; (C) at least one adjustable collimator device; (D) at least one shutter; and (E) at least one high resolution gamma ray spectrometer.

Abstract: The present invention relates generally to the field of medical isotope production by fission of uranium-235 and the fuel utilized therein (e.g., the production of suitable Low Enriched Uranium (LEU is uranium having 20 weight percent or less uranium-235) fuel for medical isotope production) and, in particular to a method for producing LEU fuel and a LEU fuel product that is suitable for use in the production of medical isotopes. In one embodiment, the LEU fuel of the present invention is designed to be utilized in an Aqueous Homogeneous Reactor (AHR) for the production of various medical isotopes including, but not limited to, molybdenum-99, cesium-137, iodine-131, strontium-89, xenon-133 and yttrium-90.

Abstract: The present invention relates generally to the field of gamma ray spectroscopy monitoring and a system for accomplishing same to monitor one or more aspects of various isotope production processes. In one embodiment, the present invention relates to a monitoring system, and method of utilizing same, for monitoring one or more aspects of an isotope production process where the monitoring system comprises: (A) at least one sample cell; (B) at least one measuring port; (C) at least one adjustable collimator device; (D) at least one shutter; and (E) at least one high resolution gamma ray spectrometer.

Abstract: The present invention relates generally to both a system and method for determining the composition of an off-gas from a solution nuclear reactor (e.g., an Aqueous Homogeneous Reactor (AHR)) and the composition of the fissioning solution from those measurements. In one embodiment, the present invention utilizes at least one quadrupole mass spectrometer (QMS) in a system and/or method designed to determine at least one or more of: (i) the rate of production of at least one gas and/or gas species from a nuclear reactor; (ii) the effect on pH by one or more nitrogen species; (iii) the rate of production of one or more fission gases; and/or (iv) the effect on pH of at least one gas and/or gas species other than one or more nitrogen species from a nuclear reactor.

Abstract: The present invention relates generally to the field of cooling systems and/or methods for cooling a heated, fissioning, or exothermic solution. In one embodiment, the present invention relates to a cooling system, and method of utilizing same, for cooling a heated, fissioning, or exothermic solution that utilizes submerged cooling coils where the system of the present invention relies on a combination of multiple factors to achieve the desired effect. In one embodiment, the present invention relates to a cooling system, and method of utilizing same, for cooling a heated, fissioning, or exothermic solution that utilizes submerged cooling coils where the system of the present invention relies on the combination of: (i) cooling coil geometry; (ii) cooling coil location and design; and (iii) cooling coil operational pressure.

Abstract: The present invention relates generally to the field of medical isotope production by fission of uranium-235 and the fuel utilized therein (e.g., the production of suitable Low Enriched Uranium (LEU is uranium having 20 weight percent or less uranium-235) fuel for medical isotope production) and, in particular to a method for producing LEU fuel and a LEU fuel product that is suitable for use in the production of medical isotopes. In one embodiment, the LEU fuel of the present invention is designed to be utilized in an Aqueous Homogeneous Reactor (AHR) for the production of various medical isotopes including, but not limited to, molybdenum-99, cesium-137, iodine-131, strontium-89, xenon-133 and yttrium-90.