Abstract: A pellet magazine includes a plurality of pellet bores sized to receive pellets for loading into a fuel rod. A fuel rod loading system includes a plurality of pellet loading stations each designated to load a single pellet type into one or more pellet bores of the pellet magazine, a rod loading station configured to unload pellets from the pellet bores of the pellet magazine into a fuel rod, and a conveyance system configured to transport the pellet magazine to the loading stations and then to the rod loading station in a defined sequence.

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 control rod drive mechanism for use in a nuclear reactor including a reactor core disposed in a pressure vessel, including a control rod configured for insertion into the reactor core, a lead screw, the control rod being secured to the bottom end of the lead screw, a drive mechanism including a torque tube having a top end and a bottom end, a pair of segment arms that are pivotably mounted to the torque tube, a pair of roller nuts, each roller nut being rotatably secured to the bottom end of a respective segment arm, and a drive motor including a stator and a rotor secured to the top end of the torque tube that includes a plurality of permanent magnets embedded therein, wherein the stator defines a central bore in which the rotor is disposed, and a latch coil assembly including a latch coil, wherein the latch coil assembly defines a central bore in which the top ends of the segment arms are disposed radially-inwardly of the latch coil.

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 nuclear fuel assembly for a nuclear reactor core, the fuel assembly having at least one fuel element including an elongated shell defining an interior volume, a lattice structure disposed within the interior volume, at least one flow channel extending through the lattice structure, at least one lattice site disposed in the lattice structure, and at least one fuel compact disposed within a corresponding one of the at least one lattice site, a first end cap including a boss having a first cross-sectional shape, the first end cap being affixed to a first end of the shell, and a second end cap including a first bore having a second cross-sectional shape, the second end cap being affixed to a second end of the shell, wherein the first cross-sectional shape of the boss is the same as the cross-sectional shape of the bore.

Abstract: A fuel rod for a nuclear reactor, including a cladding tube having a first end with an annular end face, a second end with an annular end face, and a cylindrical body portion extending therebetween, and a first tube end plug including a front portion, an annular lip with an annular end face, and a substantially straight cylindrical body portion extending therebetween, wherein the surface area of the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are substantially equal, and the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are connected by a resistance pressure weld.

Abstract: A fuel rod for a nuclear reactor, including a cladding tube having a first end with an annular end face, a second end with an annular end face, and a cylindrical body portion extending therebetween, and a first tube end plug including a front portion, an annular lip with an annular end face, and a substantially straight cylindrical body portion extending therebetween, wherein the surface area of the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are substantially equal, and the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are connected by a resistance pressure weld.

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 control rod drive mechanism for use in a nuclear reactor including a reactor core disposed in a pressure vessel, including a control rod configured for insertion into the reactor core, a lead screw, the control rod being secured to the bottom end of the lead screw, a drive mechanism including a torque tube having a top end and a bottom end, a pair of segment arms that are pivotably mounted to the torque tube, a pair of roller nuts, each roller nut being rotatably secured to the bottom end of a respective segment arm, and a drive motor including a stator and a rotor secured to the top end of the torque tube that includes a plurality of permanent magnets embedded therein, wherein the stator defines a central bore in which the rotor is disposed, and a latch coil assembly including a latch coil, wherein the latch coil assembly defines a central bore in which the top ends of the segment arms are disposed radially-inwardly of the latch coil.

Abstract: A pellet magazine includes a plurality of pellet bores sized to receive pellets for loading into a fuel rod. A fuel rod loading system includes a plurality of pellet loading stations each designated to load a single pellet type into one or more pellet bores of the pellet magazine, a rod loading station configured to unload pellets from the pellet bores of the pellet magazine into a fuel rod, and a conveyance system configured to transport the pellet magazine to the loading stations and then to the rod loading station in a defined sequence.

Abstract: A fuel rod for a nuclear reactor, including a cladding tube having a first end with an annular end face, a second end with an annular end face, and a cylindrical body portion extending therebetween, and a first tube end plug including a front portion, an annular lip with an annular end face, and a substantially straight cylindrical body portion extending therebetween, wherein the surface area of the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are substantially equal, and the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are connected by a resistance pressure weld.

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 fuel rod for a nuclear reactor, including a cladding tube having a first end with an annular end face, a second end with an annular end face, and a cylindrical body portion extending therebetween, and a first tube end plug including a front portion, an annular lip with an annular end face, and a substantially straight cylindrical body portion extending therebetween, wherein the surface area of the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are substantially equal, and the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are connected by a resistance pressure weld.

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 fuel rod for a nuclear reactor, including a cladding tube having a first end with an annular end face, a second end with an annular end face, and a cylindrical body portion extending therebetween, and a first tube end plug including a front portion, an annular lip with an annular end face, and a substantially straight cylindrical body portion extending therebetween, wherein the surface area of the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are substantially equal, and the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are connected by a resistance pressure weld.

Abstract: An end cap for a nuclear fuel rod and methods of welding the end cap to a cladding tube, particularly an HT9 end cap to an HT9 cladding tube, such as by resistance pressure welding or pressure resistance welding. The end cap includes an annular shoulder and an angled recess. Also provided are welding techniques and techniques for classifying fuel rod welds.