A system and method for consolidating used nuclear fuel rods using tools operably suspendable in a recess containing the used nuclear fuel rods. The systems and methods safely consolidate the used nuclear fuel rods in containers.

A method including providing an internal control rod drive mechanism (CRDM) including an electric motor and a support surface including sealed electrical connectors electrically connected with the electric motor to deliver electrical power to the electrical motor, installing the internal CRDM inside a nuclear reactor, the installing including placing the support surface of the internal CRDM onto a support element inside the nuclear reactor, the placing causing sealed electrical connectors disposed on the support element to mate with the sealed electrical connectors on the support surface of the internal CRDM, wherein the nuclear reactor contains coolant water and the installing is performed with the internal CRDM submerged in the coolant water and the seals of the sealed electrical connectors of the internal CRDM and the support element are effective to prevent coolant water ingress into the sealed electrical connectors.

A method whereby signals that are output by replacement SPNDs are converted into equivalent signals that would have been detected by legacy SPNDs for input to the legacy software. The replacement SPNDs have a different geometry than the legacy SPNDs and also have a different neutron sensitivity than the legacy SPNDs. The replacement SPNDs are subjected to a neutron flux in a core of a reactor and responsively output a set of signals. The set of signals and the geometry of the replacement SPNDs are employed to create a characterization of the neutron flux in the form of a curve that represents flux as a function of location along the core of the reactor. The legacy geometry of the legacy SPNDs is then employed to find the values on the curve that correspond with the positions where the legacy SPNDs had been located to create inputs for the legacy software.

The present disclosure provides a lifting and transport device for lifting upper internals from a reactor core of a nuclear power generation system in a deployment location and transporting them to a storage location. The lifting/transport device comprises a device body formed of radioactive shielding material, the device body defining a storage chamber having an open base. The device further comprises a movable sealing plate formed of radioactive shielding material, the sealing plate being movable between an open position in which the storage chamber is open and a closed position in which the storage chamber is sealed. There is also a lifting system mounted within the storage chamber having a lifting rig for releasable connection to the upper internals and configured to raise the upper internals to within the storage chamber when the device is in the deployment location and the plate is in the open position. The device comprises wheels for guiding movement of the lifting/transport device between the deployment location and the storage location.

Disclosed is a nuclear power generation system comprising a reactor vessel comprising a body defining a cavity housing a reactor core, and an integrated head package having a closure head for closing an opening to the cavity. The system also comprises a containment structure having a working floor surrounding and substantially vertically aligned with the opening to the cavity.

A repairing system (2) is used for applying an adhesive to a location to be repaired underwater in a container. The repairing system (2) comprises a movable and remotely controlled repairing robot (10) that is configured to be driven underwater. The repairing robot (10) comprises a repairing module (12) that is configured to be coupled with an adhesive applying module (34). The adhesive applying module (34) is configured to dispense an adhesive on the location to be repaired. Further, a repairing method is described.

A method for sealing an opening extending radially from an outer circumferential surface to an inner circumferential surface of a tubular object in a nuclear power plant includes inserting a stopper from outside of the outer circumferential surface through the opening into the tubular object; and actuating a fastener from the outside of the circumferential surface to force the stopper radially outward to seal the opening. A mechanical seal assembly for plugging an opening in a tubular object by contacting an inner circumferential surface of the tubular object includes a stopper configured for insertion into an interior of the tubular object for plugging the opening. The stopper includes a surface configured for matching the inner circumferential surface of the tubular object. The mechanical seal assembly also includes a fastener passing through a hole in the stopper such that the fastener is actuatable from outside of the tubular object to force the surface of the stopper against the inner circumferential surface of the tubular object.

A tool is receivable into an interior region of a core shroud of a Boiling Water Reactor. The tool includes an elongated frame, an elevator apparatus situated on the frame, and a manipulator apparatus situated on the elevator apparatus. The tool further includes a reciprocation apparatus that is situated on the manipulator apparatus and that has a mount that is structured to carry a device thereon. The reciprocation apparatus includes an elongated rack of an arcuate profile. The elevator apparatus is operable to move the reciprocation apparatus along the longitudinal extent of the frame. The tool further includes a foot apparatus that is situated at an end of the frame and that is receivable on a core plate to enable the frame to be pivoted about an axis of elongation of the frame with respect to the core plate.

A plurality of signal anomalies are identified in a number of tubes in a steam generator. Since the geometry of the steam generator is known, the location of each signal anomaly along each tube is converted into a location within the interior of the steam generator. If a plurality of signal anomalies are at locations within the steam generator that are within a predetermined proximity of one another, such a spatial confluence of signal anomalies is determined to correspond with a loose part situated within the steam generator. Additional methodologies can be employed to confirm the existence of the loose part. Historic tube sheet transition signal data can be retrieved and subtracted from present signals in order to enable the system to ignore the relatively strong eddy current sensor signal of a tube sheet which would mask the relatively weak signal from a loose part at the tube sheet transition.

An apparatus for performing an inspection on the beams of the top guide of a BWR includes a housing, an alignment assembly, and an inspection system. The housing is receivable atop the upper edges of a first pair of beams adjacent a receptacle of the top guide. The reception of the housing atop the upper edges of the first pair of beams is facilitated by the alignment assembly which includes a plurality of legs that are simultaneously moved between a retracted position wherein one or more of the legs is disengaged from the beams within the receptacle and an extended position wherein all of the legs are engaged with the beams of the top guide within the receptacle. The inspection system includes a pair of inspection elements that are translated above a second pair of beams that are adjacent the receptacle and that do not have the housing received thereon.