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 system and method for waste reclamation by which dissolved molybdenum (Mo) is reclaimed and heavy metals are filtered from process wash water containing Mo for onsite disposal. The system and method reduces byproduct cost by converting liquid byproduct to solid byproduct, while converting dissolved Mo in solution into a solid form capable of being converted to base metal.

Abstract: An elution generator including an elution column having a container defining an interior volume and a septum, a radiation shield having an upper shield portion defining a central recess and a coaxial flow needle extending downwardly into the central recess, and a lower shield portion having body portion defining a central recess, wherein the elution column is disposed in the central recess of the lower shield portion, the body portion of the lower shield portion is disposed in the central recess of the upper shield portion, and the coaxial flow needle extends downwardly through the septum into the internal volume of the elution column.

Abstract: Additive manufacturing methods use a surrogate slurry to iteratively develop an additive manufacturing protocol and then substitutes a final slurry composition to then additively manufacture a final component using the developed additive manufacturing protocol. In the nuclear reactor component context, the final slurry composition is a nuclear fuel slurry having a composition: 30-45 vol. % monomer resin, 30-70 vol. % plurality of particles of uranium-containing material, >0-7 vol. % dispersant, photoactivated dye, photoabsorber, photoinitiator, and 0-18 vol. % (as a balance) diluent. The surrogate slurry has a similar composition, but a plurality of surrogate particles selected to represent a uranium-containing material are substituted for the particles of uranium-containing material. The method provides a means for in-situ monitoring of characteristics of the final component during manufacture as well as in-situ volumetric inspection.

Abstract: Additive manufacturing methods use a surrogate slurry to iteratively develop an additive manufacturing protocol and then substitutes a final slurry composition to then additively manufacture a final component using the developed additive manufacturing protocol. In the nuclear reactor component context, the final slurry composition is a nuclear fuel slurry having a composition: 30-45 vol. % monomer resin, 30-70 vol. % plurality of particles of uranium-containing material, >0-7 vol. % dispersant, photoactivated dye, photoabsorber, photoinitiator, and 0-18 vol. % (as a balance) diluent. The surrogate slurry has a similar composition, but a plurality of surrogate particles selected to represent a uranium-containing material are substituted for the particles of uranium-containing material. The method provides a means for in-situ monitoring of characteristics of the final component during manufacture as well as in-situ volumetric inspection.

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 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 system for analyzing radiochemical purity of an eluate produced from a generator is provided. The system has an elution detector made of a shielding metal. The elution detector houses a flow path template for flow of an eluate solution and an elutable isotope contained in the generator, and a monitoring device for simultaneously monitoring the generator and the eluate exiting the generator. The generator is a Technetium-99m (Tc-99m) generator, and the elutable isotope may be contained in a packed bed of a column in the Tc-99m generator. A method for analyzing radiochemical purity of eluate produced from a Technetium-99m (Tc-99m) generator or column is also provided.

Abstract: An elution generator including an elution column having a container defining an interior volume and a septum, a radiation shield having an upper shield portion defining a central recess and a coaxial flow needle extending downwardly into the central recess, and a lower shield portion having body portion defining a central recess, wherein the elution column is disposed in the central recess of the lower shield portion, the body portion of the lower shield portion is disposed in the central recess of the upper shield portion, and the coaxial flow needle extends downwardly through the septum into the internal volume of the elution column.

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 system for analyzing radiochemical purity of an eluate produced from a generator is provided. The system has an elution detector made of a shielding metal. The elution detector houses a flow path template for flow of an eluate solution and an elutable isotope contained in the generator, and a monitoring device for simultaneously monitoring the generator and the eluate exiting the generator. The generator is a Technetium-99m (Tc-99m) generator, and the elutable isotope may be contained in a packed bed of a column in the Tc-99m generator. A method for analyzing radiochemical purity of eluate produced from a Technetium-99m (Tc-99m) generator or column is also provided.

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.