General Electric Company

Areva Gmbh

Fred Charles Nopwaskey

Ke Ling Lee

Hsueh-Wen Na Pao

Gary Allen Boortz

Alfred Wilhelm Dalcher

Frank Ortega

Robert W Whitling

Bettadapur N Sridhar

Balasubramanian S Kowdley

Randy Morse Villeneuve

Stephen K Parker

Ryan Michael Welsh

Stephan Mark Hunter

Frank C Falzone

Joel J Letourmy

The method includes repairing a nuclear reactor, where the reactor includes one or more submerged lines welded to one or more support brackets. The method involves removing a damaged section of the one or more submerged lines, and replacing the damaged section without welding.

Method and apparatuses for operating and repairing nuclear reactors

A clamp for a boiling water reactor feedwater sparger is disclosed and claimed. The clamp assembly includes abuse and cooperating bolt, a reaction arm, and a cross pin. With the exception of the cross pin, the parts are pre-assembled and then installed over the sparger pin head. The cross pin is then installed through the clamp base and through the sparger pin. The clamp bolt is then tightened, locking the clamp and sparger pin. The clamp provides an increased surface area that extends 360&#xb0; around the sparger pin. This increased surface area reduces the likelihood of wear of the clamp or bracket during plant operation, and the clamp restores the position of the sparger pin head relative to the contact surface of the end bracket if the original pin head or bracket is worn.

BWR feedwater sparger end bracket pin clamp

Method of repairing nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: removing a damaged section of one of the one or more submerged lines; and replacing the damaged section of the one of the one or more submerged lines without welding. Methods of operating nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: shutting down the nuclear reactor; repairing damage to at least one of the one or more submerged lines without welding; and starting up the nuclear reactor. Methods of operating nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: cooling down the nuclear reactor; repairing damage to at least one of the one or more submerged lines without welding; and heating up the nuclear reactor.

Methods and apparatuses for operating and repairing nuclear reactors

An ultra high pressure abrasive waterjet cutting apparatus for cutting nuclear reactor structural components is described. The cutting apparatus includes an ultra high pressure abrasive waterjet (UHP) cutting nozzle, movably coupled to a single axis manipulator, and a collection hood. The manipulator and the collection hood are coupled to a support frame and are configured to be positioned inside adjacent openings of a nuclear reactor top guide or core plate so that the cutting nozzle is in alignment with the collection hood. The manipulator includes a linear frame, a nozzle support plate movably coupled to the linear frame, and a motor operatively coupled to the nozzle support plate. The collection hood includes an elongate collection chamber having an elongate opening located so that the opening is in alignment with the cutting nozzle. The collection hood also includes at least one positioning cylinder coupled to the collection chamber and to the support frame which positions the collection chamber opening adjacent a top guide or core plate beam. The collection hood further includes an outlet port configured to be connected to a water filtration system.

Ultra high pressure abrasive waterjet cutting apparatus

An ultra high pressure abrasive waterjet cutting apparatus for underwater cutting of structural components of a nuclear reactor is described. The cutting apparatus includes a multi-axis manipulator, an ultra high pressure abrasive waterjet (UHP) cutting nozzle coupled to the manipulator, a collection stand assembly, a collection hood movably coupled to the collection stand assembly, and a turntable having a non-movable center portion. The multi-axis manipulator is configured to mount on the non-movable center portion of the turntable or on the floor of the pool of water in which the structural component is positioned for cutting. The collection stand assembly is configured to mount on at least one of the floor and the wall of the pool of water. The cutting nozzle and collection hood are positioned on opposite sides of the structural component to be cut.

Floor mounted ultra high pressure abrasive cutting apparatus

A lifting fixture includes a housing; a plurality of jaws movable radially in and out of the housing to secure the fixture to a component to be lifted; at least one lifting bail extending from on end of the housing; and a screw mechanism operatively connected to the plurality of jaws for moving the jaws radially between an inward retracted position and an outward locking position. A related lifting and flipping process is also disclosed.

Core plate lifting fixture and related process

A tool set and a method of using those tools in combination is disclosed that are especially well adapted to the function of rearranging and/or replacing the control rods and fuel supports in a boiling water reactor. The tool set includes a grapple that is capable of simultaneously picking up both a control rod and its associated fuel support. A separate unlatching tool is provided for pulling the control rod's release handle in order to decouple the control rod from a control rod drive. A storage rack that may be mounted in the reactor pressure vessel is provided for storing a fuel support and a pair of control rods when the positions of selected control rods are being shifted about the reactor core area. In the method aspect of the invention, the unlatching tool is used to pull the control rod's release handle. Thereafter, the grapple lifts the control rod and its associated fuel support as a unit. When rearranging the positions of the control rods, a first control rod and its associated fuel support are placed the storage rack. Then a second control rod/fuel support assembly is removed in a similar manner and the second control rod is placed in the storage rack. Thereafter, the first control rod may be removed from the storage rack and placed in the position formally occupied by the second control rod, with the same fuel support that was removed from the second location.

Growing community of inventors

San Jose, CA, United States of America

Fred Charles Nopwaskey