General Electric Company

Ge-hitachi Nuclear Energy Americas LLC

Global Nuclear Fuel - Americas, LLC

Russell Patrick Higgins

David Grey Smith

William Earl Russell, Ii

Russell M Fawcett

Russell Edward Stachowski

Michael T Kiernan

Robert Bryant James

Lukas Trosman

Steven Bruce Shelton

Randy Peter Gonzales

Robert B Elkins

Harold B King

Gerald M Latter

Edward A Croteau

Christian D Frederickson

Vernon W Mills

Russell Morgan Fawcett

Michael Thomas Kiernan

John L Harmon

Michael Scott DeFilippis

Carlton Wayne Clark

Thomas G Dunlap

Anthony P Reese

Edward G Apple

David W White

Gerald Anthony Luciano

Bradley D Bloomquist

Christopher J Monetta

Michael S Defilippis

Bob Y Okashima

Richard G Patterson

Roger Howard Van Slyke

Gary I Borchardt

Peter A Peterson

William Williams

Thomas G Evans

Stephanie Baker Lindquist

William Earl Russell

William Earl Russell Ii

Ii Russell William Earl

Ii William Earl Russell

One embodiment provides a multi-segment rod that includes a plurality of rod segments. The rod segments are removably mated to each other via mating structures in an axial direction. An irradiation target is disposed within at least one of the rod segments, and at least a portion of at least one mating structure includes one and/or more combinations of neutron absorbing materials.

Rod assembly for nuclear reactors

An isotope production target rod for a power generating nuclear reactor is provided. The isotope production target rod can include at least one rod central body including an outer shell that defines an internal cavity and a plurality of irradiation targets within the internal cavity. The irradiation targets can be positioned in a spatial arrangement utilizing a low nuclear cross-section separating medium to maintain the spatial arrangement.

Cross-section reducing isotope system

In a method of producing isotopes in a light water power reactor, one or more targets within the reactor may be irradiated under a neutron flux to produce one or more isotopes. The targets may be assembled into one or more fuel bundles that are to be loaded in a core of the reactor at a given outage. Power operations in the reactor irradiate the fuel bundles so as to generate desired isotopes, such as one or more radioisotopes at a desired specific activity or stable isotopes at a desired concentration.

Method of producing isotopes in power nuclear reactors

A fuel assembly may include a channel nosepiece; a lower tie plate positioned above the channel nosepiece; and at least one bundle retention clip connected to the channel nosepiece and the lower tie plate and configured to resist movement of the lower tie plate away from the channel nosepiece.

Bundle retention clip, fuel assembly including the same, and method of assembling fuel assembly

A rod assembly for a fuel bundle of a nuclear reactor may include an upper end piece, lower end piece and a plurality of rod segments attached between the upper and lower end pieces and to each other so as to form an axial length of the rod assembly. The rod assembly may include an adaptor subassembly provided at given connection points for connecting adjacent rod segments or a given rod segment with one of the upper and lower end pieces. The connection points along the axial length of the rod assembly may be located where the rod assembly contacts a spacer in the fuel bundle. One (or more) of the rod segments may include an irradiation target therein for producing a desired isotope when a fuel bundle containing one (or more) rod assemblies is irradiated in a core of the reactor.

In various embodiments, a spacer grid for a nuclear reactor fuel bundle is provided. The grid includes a plurality of interstitial dividers that form an array of cells. Each cell is structured to retain a respective one of a plurality of fuel rods to thereby form an array of equally spaced fuel rods. The grid additionally includes a perimeter band that peripherally surrounds the dividers and is connected to opposing ends of each divider. The perimeter band includes a plurality of spring tabs formed along and extending from an edge of the perimeter band. The spring tabs extend from the edge at an angle away from the dividers such that a distal end of each spring tab will contact an interior surface of a respective one of a plurality of walls of a channel in which the arrayed fuel rods can be inserted to form the fuel bundle.

Fuel bundle and spacer band

An apparatus for measuring perpendicularity of an upper tie plate of a nuclear fuel bundle includes a first comb having a first plurality of teeth; a second comb having a second plurality of teeth, the second comb being parallel to and spaced from the first comb; a comb connector that connects the first comb to the second comb, the comb connector having a second end extending beyond the first comb; a rigid finger provided at the second end of the comb connector; a rotatable gage provided on the second comb; and a mobile finger operatively connected to the gage.

Apparatus and method for measuring and setting perpendicularity of an upper tie plate of a nuclear fuel bundle

The spacer/water rod retention assembly includes a clip secured to the spacer having a slot perimetrically bounded both axially and laterally spaced portions of the clip. A resilient tab projects from one side portion into the slot. A water rod has a projecting tab which, upon relative rotation of the spacer and water rod, engages and deflects the clip tab to enable the water rod tab to reside in the clip slot. When the clip tab returns to its initial position, substantial relative rotation between the water rod and spacer is precluded and axial connection between the spacer and water rod is assured. In another form, the water rod tab projects into a slot of the clip. An adjacent water rod prevents rotation of the water rod tab in the opposite direction, thereby capturing the spacer and water rod and preventing relative axial movement.

Fuel spacer/water rod capture apparatus and methods for boiling water nuclear reactors

The spacer comprises a plurality of strips interleaved with one another to form an eggcrate-type pattern defining essentially rectilinear cells for each fuel rod. Each strip includes a central body portion with cantilevered loop spring-like projections extending to opposite sides, with spring contact portions projecting inwardly. Stops are provided along each of the central body regions of the strips intermediate the loop springs that project to the opposite side of the strip. Adjoining walls have loop spring portions for biasing the rod into engagement with opposing stops whereby each fuel rod is supported at six contact points, i.e., four spring contact points and two hard stop contacts opposite the paired spring contacts.

Multi-spring strip spacer for nuclear fuel bundles

In a nuclear reactor fuel bundle assembly having a plurality of fuel rods and a non-round water rod extending between upper and lower tie plates, and having at least one fuel rod spacer located along the non-round water rod, an improvement which includes cooperating components on the fuel rod spacer and on the water rod for permitting movement of the spacer along the water rod to a desired axial location and for thereafter preventing further axial movement of the spacer in at least one of two opposite axial directions, the cooperating components including at least one spring on one of the spacer and the water rod.

Spacer capture mechansim for non-round water rods

A fuel assembly for a nuclear reactor vessel includes a plurality of fuel rods, at least one coolant rod, a lower tie plate supporting the fuel rods and coolant rod, and a channel surrounding the fuel rods, coolant rod and tie plate. The lower tie plate is supported by the channel such that the channel carries a load of the fuel assembly. In one aspect of the invention, an upper tie plate includes two spring loaded latch pins engageable with corresponding apertures in the channel. A transition member supports the lower tie plate and is rigidly secured to the channel. Thus, when lifting the fuel assembly from the reactor, the channel bears the load of the fuel assembly. End gussets or clips are welded to the channel and inserted into the transition member, which serve as a secondary support for the transition member in the event that its primary connection to the channel fails. A channel guide member is secured to the, upper tie plate and includes two ears that are received in ear apertures in the channel. The channel guide and ears thus provide a redundant attachment between the tie plate and the channel in the event that the spring loaded latch pins fail. If it is desired to remove the fuel bundle from the channel, the upper tie plate is released from the assembly by detaching the guide member and releasing the spring loaded latch pins. The bundle can then be removed from the channel by attaching a grapple head to the coolant rod ends, which are specially shaped to facilitate an attachment tool.

Fuel assembly structure using channel for load support

A part length fuel rod tip and group of tip grasping tools is set forth for the removal, inspection and replacement of part length fuel rods from a fuel bundle having a part length rods interspersed with a majority of conventional full length rods. The part length fuel rod tip includes a longitudinal keyway allowing torque to be exerted on the fuel rod and a horizontal slot enabling grasping of the fuel rod for vertical withdrawal and replacement movement of the fuel rod. The tools include a torque socket for applying high torque forces to the part length rod for unscrewing the rod when the rod becomes stuck at its threaded connection to the lower tie plate, a tip grasping tool for permitting normal unscrewing torque and grasping for vertical withdrawal and replacement, and finally a tool having both high torque and grasping characteristics. In each case, the diameter of the tools is restricted to enable access to the part length fuel rods through the spacers overlying the upwardly exposed ends of the part length fuel rods.

Partial length rod upper end plug and grapples therefor

Growing community of inventors

Wilmington, NC, United States of America

Russell Patrick Higgins