Westinghouse Electric Corporation

Westinghouse Electric Company LLC

Douglas E Ekeroth

Luciano Veronesi

James E Gillett

Donald G Sherwood

Ronald J Hopkins

John T Land

Denis J Altman

Michael J Hurwitz

Richard S Orr

Daniel C Garner

John M Matusz

Michael M Corletti

David Squarer

F Thomas Johnson

Raman G Patel

Rossemary V Chavez

Matthew M Rohr

Abby L Stemler

Christopher F Herleman

Arthur W Francis

Daniel L Walters

Elongated coolant pumps suspended under steam generators within containment in a power plant with limited access space, are removed and replaced by an elongated maintenance cart with an elongated opening along one side in which the motor is received. Rollers support the cart for conveying the elongated motor in an upright position out from under the steam generator and onto an elevator. The elevator is lowered to transfer support of the cart and motor through trunnions to saddles straddling the elevator for rotation of the cart to a generally horizontal position. The elevator then raises the horizontally disposed cart carrying the motor to a higher floor where it is rolled off the elevator and out through the auxiliary equipment hatch.

Apparatus and method for servicing an elongated suspended pump motor in

Instrumentation for nuclear reactor head-mounted incore instrumentation systems fabricated of low nuclear cross section materials (i.e., zirconium or titanium). The instrumentation emits less radiation than that fabricated of conventional materials.

Low activated incore instrument

A nuclear reactor is provided having a generally cylindrical reactor vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The reactor vessel is supported within the opening in the primary shield by reactor vessel supports which are in communication and aligned with central portions of some of the side walls. The reactor vessel is connected to the central portions of the reactor vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the reactor vessel and is disposed between the reactor vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield. Reactor monitoring instrumentation may be mounted in the corners of the opening in the primary shield between the side walls and the reactor vessel such that insulation is not disposed between the instrumentation and the reactor vessel.

Nuclear reactor having a polyhedral primary shield and removable vessel

An apparatus and method are provided for suppressing the formation of vortices in circulating coolant fluid of a nuclear reactor. A vortex-suppressing plate having a plurality of openings therein is suspended within the lower plenum of a reactor vessel below and generally parallel to the main core support of the reactor. The plate is positioned so as to intersect vortices which may form in the circulating reactor coolant fluid. The intersection of the plate with such vortices disrupts the rotational flow pattern of the vortices, thereby disrupting the formation thereof.

Apparatus for suppressing formation of vortices in the coolant fluid of

A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet.

Locating hot and cold-legs in a nuclear powered steam generation system

A hydroball string sensing system for a nuclear reactor that includes stainless tubes positioned to guide hydroball strings into and out of the nuclear reactor core. A sensor such as an ultrasonic transducer transmitter and receiver is positioned outside of the nuclear reactor core and adjacent to the tube. The presence of an object such a bullet member positioned at an end a hydroball string, or any one of the hydroballs interrupts the transmission of ultrasound from the transmitter to the receiver. Alternatively, if the bullet member and hydroballs include a ferritic material, either a Hall effect sensor or other magnetic field sensors such as a magnetic field rate of change sensor can be used to detect the location and position of a hydroball string. Placing two sensors along the tube with a known distance between the sensors enables the velocity of a hydroball string to be determined. This determined velocity can be used to control the flow rate of a fluid within the tube so as to control the velocity of the hydroball string.

Hydroball string sensing system

A stepping apparatus uses two gate elements driven by solenoid actuators to block a detector string as it is advanced to a gamma counter so that the string can be advanced at a controlled rate, one ball at a time. The gate elements each have two interconnected passages, one of which permits passage of the entire detector string, while the other permits passage of the cable but not the balls.

Hydroball detector string stepping device

A pressurized water reactor of an advanced design comprises, in vertically spaced relationship, a lower barrel assembly having lower and upper core plates, an inner barrel assembly and an axially removable calandria assembly having a lower calandria plate. A plurality of rod guides are cantilever-mounted in parallel axial relationship within the inner barrel assembly and, specifically, are rigidly mounted at the lower ends thereof to the upper core plate. Axially extending sleeves are affixed to the upper ends of the rod guides and telescopingly receive therein generally cylindrical supports which are affixed to and depend downwardly from the lower calandria plate and define alignment axes for the respectively associated rod guides. Links are secured at first ends to the mount and extend radially therefrom at angularly displaced positions, second, free ends of the links being free to move in pivotal rotation from a normal, downward and radially inward position to an upward and radially outward position, when engaged by receiving means formed in the upper ends of the sleeves as the calandria assembly is moved into assembled relationship with the inner barrel assembly. In the assembled relationship, the links, moved fully to the upward and radially outward positions, produce resilient, lateral loading between the respective sleeves and cylindrical mounts and maintain alignment of the associated sleeves and rod guides with the respective alignment axes.

Resiliently loaded lateral supports for cantilever-mounted rod guides of

A support for the top ends of plural rod guides of at least first and second types which are generally vertically disposed within a pressurized water reactor vessel in corresponding, first and second interleaved matrices. Lower ends of the rod guides are affixed to a lower support structure and the upper ends thereof are disposed adjacent to and spaced vertically below an upper support structure of the vessel. Corresponding, first and second types of top support plates are disposed on and connected to respective top ends of the first and second types of rod guides. The first and second types of top support plates have mating exterior peripheral surfaces which are assembled in sliding, telescoping relationship, a transverse extension from one peripheral surface being received in a vertically extending, recessed channel in a mating peripheral surface of the contiguous support plates. A linkage is secured to a top support plate of one type and to each of the mating top support plates of the other type contiguously surrounding it, providing rigid lateral interconnection and resilient vertical interconnection of the top plates and maintaining same in a concatenated relationship. Aligned keyway segments of the assembled and contiguous first and second plates receive keys which are bolted in place and provide limit stops to relative displacement of the contiguous, interconnected plates.

Simplified, flexible top end support for cantilever-mounted rod guides

An array of plural rod guides each housing therewithin corresponding pluralities of rods, as disposed in parallel axial relationship within the cylindrical sidewall of the inner barrel assembly of a pressurized water reactor, defines a plurality of peripheral regions between the inner circumferential surface of the cylindrical sidewall and the peripheral edges of the array. A plurality of modular formers is installed within the respective plurality of peripheral regions, at each of one or more banks of predetermined, respective elevations within the inner barrel assembly. Each modular former comprises a pair of parallel former plates having arcuate outer edges corresponding to the interior circumference of the cylindrical sidewall and chordlike inner edges contoured to correspond to the juxtaposed peripheral edge of the array, and a vertical column extending between and rigidly interconnecting the associated plates of a pair. Attachment means secured to the surfaces of the plates extend beyond the respective outer arcuate edges thereof and through holes provided therefore in the cylindrical sidewall and are welded thereto from the exterior surface of the sidewall. One more banks of modular formers, as required, establish the proper pressure drop of the core output flow from the lower barrel assembly so as to approach an axial flow condition within the inner barrel assembly, reducing turbulance and minimizing vibration in operation.

Modular former for inner barrel assembly of pressurized water reactor

A top end support for rod guides disposed in closely spaced, parallel axial relationship within an inner barrel assembly of a pressurized water reactor vessel includes, in telescoping relationship, a generally cylindrical support having an end closure with a central aperture therein for receiving a downwardly depending extension from a lower calandria plate and a sleeve having an outer periphery corresponding in cross-section to that of said rod guide and affixed thereto at its lower end, the sleeve having an interior, generally cylindrical surface for receiving the cylindrical support in close engagement therein. The telescopingly engaged, generally cylindrical surfaces of the cylindrical support and the sleeve provide substantial area to function as a long-life wear couple. Both the end closure and the cylindrical sidewalls of the fixed cylindrical support and the interior surface of the sleeve are configured so as to correspond to the perimeter of flow holes disposed in a symmetrical array about the associated depending extension, to permit unimpeded passage therethrough of the core outlet flow.

Growing community of inventors

Delmont, PA, United States of America

Douglas E Ekeroth