Patent classifications
G21C19/207
SYSTEMS AND METHODS FOR UNDERWATER TOOL POSITIONING
Systems and methods position tools about a flooded nuclear reactor during maintenance outages without overhead support or alignment structures being necessary. systems may include annular clamps for support from a reactor steam dam, a telescoping mast, a motor or other drive to extend or retract the mast, and/or an articulator to hold the payload and move the same about any degree of freedom. The telescoping mast may include several nested sections joined to a drive motor. Several different articulators are useable, including those with separate gearings for rotation about perpendicular axes and self-leveling wrists to orient tools in confirmed positions. Systems can be locally or remotely powered and controlled through powered and communicative connections to move about any position in a reactor annulus or core.
Systems and methods for reducing surface deposition and contamination
Mobile apparatuses move within contaminated fluid to create fluid flows against structures that remove and prevent contaminant deposition on structure surfaces immersed in the fluid. Unsettling flows in water may exceed approximately 2 m/s for radionuclide particles and solutes found in nuclear power plants. Mobile apparatuses include pressurized liquid from a pump or pressurized source that can be chemically and thermally treated to maximize deposition removal. When spraying the pressurized liquid to create the deposition-removing flow, mobile apparatuses may be self-propelled within the fluid about an entire surface to be cleaned. Mobile apparatuses include filters keyed to remove the contaminants moved into the coolant by the flow, and by taking in ambient fluid, enable such filtering of the ambient fluid along with a larger flow volume and propulsion. Propulsion and the pressurized liquid in turn enhance intake of ambient fluid.
Apparatuses and methods for structurally replacing cracked welds in nuclear power plants
An apparatus configured to structurally replace a cracked weld in a nuclear plant may include: a first body portion that includes a first gripping portion; a second body portion that includes a second gripping portion; a wedge portion between the first and second body portions; and/or an adjustment portion. The first body portion may be configured to slidably engage the second body portion. The wedge portion may be configured to exert force on the slidably engaged first and second body portions. The adjustment portion may be configured to increase or decrease the force exerted by the wedge portion on the slidably engaged first and second body portions. When the adjustment portion increases the force exerted by the wedge portion on the slidably engaged first and second body portions, a distance between the first and second gripping portions may decrease.
Apparatus for use in the inspection of a top grid guide of boiling water reactor
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.
Method of cleaning a throat section of a jet pump assembly of a nuclear reactor
A method of cleaning a jet pump assembly of a nuclear reactor may comprise inserting a cleaning tool into the jet pump assembly such that a front face of the cleaning tool is adjacent to an inner surface of the jet pump assembly and below a level of a first liquid in the jet pump assembly. The method may additionally comprise directing a plurality of front jets of a second liquid from a plurality of front orifices on the front face of the cleaning tool such that the plurality of front jets of the second liquid strikes the inner surface of the jet pump assembly. The method may further comprise maintaining a standoff distance between the front face of the cleaning tool and the inner surface of the jet pump assembly during the cleaning of the jet pump assembly.
Assembly for acting on the outer surface of a tube, and corresponding method
An assembly for acting on the outer surface of a tube, and corresponding method are provided. The assembly includes a carrier; at least one inspection or maintenance tool; the carrier includes at least one rolling body; an actuator. The carrier further includes a device for connecting the carrier to the tube, arranged so that the tube absorbs at least 50% of the weight of the carrier and the tool.
Inspection tool
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.
Detection apparatus and method of detecting the neutron absorption capability of a control element of a nuclear installation
A detection apparatus is usable to detect the neutron absorption capability of a control element of a nuclear installation and includes a neutron radiograph apparatus and a robot apparatus. The neutron radiograph apparatus includes a neutron emission source of variable strength, a detector array, a mask apparatus and a positioning robot all under the control of a central processor and data acquisition unit. The neutron emission source is advantageously switchable between an ON state and OFF state with variable source strength in the ON state, which avoids any need for shielding beyond placing the neutron emission source in an inspection pool at the nuclear plant site including but not limited to the spent fuel or shipping cask laydown pools. The neutron emission source is situated at one side of a wing of the control element and generates a neutron stream, the detector array is situated on an opposite side of a wing, and the neutron emission source and detector array are robotically advanced along the wing. The detector array is monitored in real time, and various masks of the mask apparatus can be positioned between the neutron emission source and the detector array to more specifically identify the position on the blade where the neutrons are passing through.
INTEGRATED HEAD PACKAGE
The present disclosure provides an integrated head package for a nuclear power generation system, the integrated head package comprising a closure head, and a control rod drive mechanism housed within a shroud. The control rod drive mechanism comprises at least one drive rod extending through the closure head and having a coupling element for releasably coupling to a control rod assembly within a reactor core. The at least one drive rod is movable to a maintenance/refuelling position in which the at least one drive rod is uncoupled from the control rod assembly and at least partially retracted into the integrated head package. The integrated head package further comprises at least one engagement feature for securing the at least one drive rod in the maintenance/refuelling position.
POSITIONING AND INSPECTION APPARATUSES FOR USE IN NUCLEAR REACTORS
Systems are provided for inspection and tooling submerged in nuclear reactors. Systems mount at the reactor edge, such as on a steam dam, to be independently operable from a refueling bridge or refueling operations. A moveable steam dam clamp may hold a position apparatus at the edge. The positioning apparatus includes a rotatable shoulder and arms move a tool, reactor component, and/or inspection device like a camera or VARD to desired and highly-determinable reactor positions. A float may counter shear and rotation on the shoulder from the arms. Motors at the shoulder with internal transmissions may rotate the shoulder and arms, or manual rotation may be used. The arms may also overlap vertically for installation and removal. Power, controls, and/or data may be provided underwater through an umbilical connection to operators.