General Electric Company

Christian D Frederickson

Robert B Elkins

Harold B King

Thomas G Dunlap

Edward A Croteau

Russell Patrick Higgins

Richard A Proebstle

David Grey Smith

John L Harmon

Gerald M Latter

Anthony P Reese

David W White

Richard G Patterson

A water rod for a fuel assembly of a boiling water nuclear reactor has a first end and a second end, wherein at least one of the first and second ends is directly attachable to a tie plate of the fuel assembly without an end plug. The structure of the present invention simplifies the manufacturing process and reduces the cost of the fuel assembly in the boiling water nuclear reactor. The water rod according to the invention has one or both of its ends configured to be directly attachable to the tie plate of the fuel assembly.

Water rod in a fuel assembly of a boiling water nuclear reactor

The spacer for a nuclear fuel bundle includes unit cells having upper and lower, generally octagonally shaped walls connected one to the other by spring leg portions along sides thereof 90.degree. apart. The walls also carry stops in opposition to the sides of the walls to which the spring leg portions are connected. By orienting the cells in the spacer such that the majority of the cells have their stops lying toward one side of the spacer, the fuel bundle can be disposed in a horizontal position on the one side of the spacers. In that manner, the dead load of the fuel rods and spacers is borne by the stops along the underside of each spacer without substantially loading the springs of the spacer cells.

Spacer for a transportable nuclear fuel rod bundle

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 lifting assembly is configured to facilitate attaching of the lifting bar to a load bearing water rod in a nuclear fuel assembly. A connecting member is rigidly secured to the water rod and is provided with one of a male engaging portion and a female receiving portion. A lifting member including the lifting bar is engageable with the connecting member and includes the other of the male engaging portion and the female receiving portion. The male engaging portion and the female receiving portion are correspondingly shaped, and after insertion of the connecting member into or about the lifting member, the connecting member and lifting bar can be rotated relative to each other to prevent disassembly of the lifting assembly. A spring is disposed between the lifting bar and the water rod and urges the male engaging portion toward a locked position. The lifting assembly facilitates the attaching and detaching of the lifting bar to a load bearing water rod.

Method and apparatus for attaching a lifting bar to a load bearing water

A fuel bundle assembly for a nuclear reactor includes a lower tie plate; a transition piece underlying the lower tie plate; a plurality of fuel rods and at least one water rod seated on the lower tie plate and extending in substantially parallel relationship toward an upper end of the fuel bundle assembly, wherein a fuel bundle assembly lifting load is carried by load bearing members including certain of the fuel rods or by the at least one water rod; a plurality of spacers axially spaced along the at least one water rod and including means for laterally supporting each of the fuel rods; and a handle bar assembly at the upper end of the fuel bundle assembly connected to the load bearing members such that the plurality of non-load bearing fuel rods are supported only by the lower tie plate and the plurality of spacers.

BWR fuel assembly without upper tie plate

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 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, a conventional upper tie plate is removed and a handle assembly is provided that 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. If it is desired to remove the fuel bundle from the channel, the handle assembly is released from the assembly by releasing the 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.

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Wilmington, NC, United States of America

Christian D Frederickson