Ge-hitachi Nuclear Energy Americas LLC

Porta-nails, Inc.

Randy Morris Brown

Gerald Alan Deaver

Kenneth Allan Morgan

David L Major

Joel Patrick Melito

Jesus G Diaz-Quiroz

Mitra Hosseini

Lorne Eugene Nix

Namon B Batts, Jr

Robin D Sprague

Adrian M Mistreanu

Filemon Tecson Cabrera

Zhe Zhang

David Lee Major

GeraldA Deaver

Control rod drives include linearly-moveable control elements inside an isolation barrier. Control rod drives move the control element through secured magnetic elements subject to magnetic fields. Induction coils may generate magnetic fields and be moveable across a full stroke length of the control element in the reactor. A motor may spin a linear screw to move the induction coils on a vertical travel nut. A control rod assembly may house the magnetic elements and directly, removably join to the control element. The control rod assembly may lock with magnetic overtravel latches inside the isolation barrier to maintain an overtravel position. Overtravel release coils outside the isolation barrier may release the latches to leave the overtravel position. Operation includes moving the induction coils with a linear screw to drive the control element to desired insertion points, including full insertion by gravity following de-energization. No direct connection may penetrate the isolation barrier.

Methods of moving an induction coil to move a control element in a nuclear reactor

Control rod drives include linearly-moveable control elements inside an isolation barrier. Control rod drives move the control element through secured magnetic elements subject to magnetic fields. Induction coils may generate the magnetic fields across a full stroke length of the control element in the reactor. A closed coolant loop may cool the induction coils, which may be in a vacuum outside the isolation barrier. A control rod assembly may house the magnetic elements and directly, removably join to the control element. The control rod assembly may lock with magnetic overtravel latches inside the isolation barrier to maintain an overtravel position. Overtravel release coils outside the isolation barrier may release the latches to leave the overtravel position. Methods of operation include selectively energizing or de-energizing induction coils to drive the control element to desired insertion points, including full insertion by gravity following de-energization. No direct connection may penetrate the isolation barrier.

Stationary isolated rod couplings for use in a nuclear reactor control rod drive

A reactor pressure vessel includes a reactor pressure vessel body, a nozzle structure connected to the reactor pressure vessel body, a conduit structure connected to the nozzle structure, and a restraint device attached around a portion of the conduit structure. The restraint device includes collar parts that have cross sections corresponding to respective segments of a periphery of the portion of the conduit structure, brackets attached to the nozzle structure, and rods connecting the brackets to the collar parts. The collar parts are connected end-to-end to each other such that a cross section of the collar parts connected to each other corresponds to the periphery of the portion of the conduit structure. The collar parts are pinned to each other. The brackets spaced apart from each other around a periphery of the nozzle structure.

Reactor pressure vessel including pipe restraint device, and/or pipe restraint device

Control rod drives include linearly-moveable control elements inside an isolation barrier. Control rod drives move the control element through a motor and rotor powering a linear screw internal to an isolation barrier. Induction coils may generate magnetic fields and be moveable across a full stroke length of the control element in the reactor. The magnetic fields hold closed a releasable latch to disconnect the control elements from the linear drives. A control rod assembly may join to the control element. The control rod assembly may lock with magnetic overtravel latches inside the isolation barrier to maintain an overtravel position. Overtravel release coils outside the isolation barrier may release the latches to leave the overtravel position. Operation includes moving the magnetic fields and releasable latch together on opposite sides of an isolation barrier to drive the control element to desired insertion points, including full insertion by gravity following de-energization.

Magnetically-actuated isolated rod couplings for use in a nuclear reactor control rod drive

Modular flow control systems include several differently-shaped structures to achieve desired flow characteristics in fluid flow. Systems include one or many plates held in desired positions by a retainer within the flow. The plates are uniquely shaped based on their position, or vice versa, to shape flow in a desired manner. The plates may fill an entire flow area or may extend partially throughout the area. Plates can take on any shape and are useable in systems installed in any type of flow conduit. When used in a PCCS upper manifold in a nuclear reactor, a chevron plate directly below the inlet divides flow along the entire upper manifold. Perforated plates allow flow to pass at ends of the PCCS upper manifold. The plates can be installed along a grooved edge during an access period and held in static position by filling the length of the PCCS upper manifold.

Modular fluid flow distribution system in which differently shaped plates can be rearranged to different positions

A flow restrictor nozzle for a pressurized vessel of a nuclear reactor may comprise a nozzle body including an inlet face and an outlet face. The nozzle body may define a plurality of internal flow paths extending from the inlet face to the outlet face. Each of the plurality of internal flow paths may include a convergent section, a throat section, and a divergent section.

Multiple-path flow restrictor nozzle

Moveable isolated rod couplings for use in a nuclear reactor control rod drive

Reactor pressure vessel including pipe restraint device, and/or a pipe restraint device

A method of shutting down a nuclear reactor may include compressing a scram gas that is in fluid communication with a scram accumulator. The scram accumulator defines a chamber therein and contains bellows within the chamber. The bellows are configured to hold a scram liquid in isolation of the scram gas. The scram gas exerts a compressive force on the bellows in a form of stored energy. The method may additionally include releasing the stored energy in response to a scram signal such that the scram gas expands into the chamber of the scram accumulator to compress the bellows and expel the scram liquid from the scram accumulator to insert control rods into a core of the nuclear reactor.

Hydraulic control unit and method of shutting down a nuclear reactor using the same

A pneumatic nailer having a safety mechanism that reduces accidental discharge of nailer is provided. The nailer includes a hollow main body housing having a main pressure chamber in pneumatic communication with a main valve housing. Pressurized gas is injected into main pressure chamber, and a metering hole between the main chamber and valve assembly allows gas pressure to equalize between the main chamber and the valve housing. A safety trigger and safety valve are in pneumatic communication with the pressurized valve housing. A ram cap positioned over the top portion of the valve assembly is struck, moving the main valve assembly downward, with unseating of a cylinder firing valve only if internal pressures have been adjusted by actuation of the safety valve by an operator. When safety valve is actuated, gas pressure drops in the valve housing, reducing pressure on the main valve side of cylinder firing valve, allowing movement of main valve and cylinder firing valve, while gas pressure flows into piston cylinder, moving downward the piston and driver blade assembly, and forcing ejection of a fastener from nailer. If safety trigger is not actuated, pressure remains constant around main valve and cylinder firing valve, remaining closed, and negating upward movement of cylinder firing valve with no movement of piston and driver blade assembly, despite striking of ram cap. Thus, the possibility of accidentally driving a fastener is virtually eliminated without operator's use of the safety trigger.

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Wilmington, NC, United States of America

Randy Morris Brown