ROBERT MEUSCHKE
Engineers in Monroeville, PA

5737377, Apr 7, 1998

Feb 5, 1996

8/596961

David J. Stefko - Jeannette PA
Robert M. Blumstein - Hempfield PA
Robert E. Meuschke - Monroeville PA
William J. Smoody - North Huntingdon PA
John A. Klimek - Oakdale PA
Edward H. Smith - Brave PA

Westinghouse Electric Corporation - Pittsburgh PA

G21C 1920, G21C 1706

376268

A camera mast system permits remote inspection of nuclear fuel assemblies and other components of nuclear reactors. The system includes a camera mast assembly mounted on a refueling mast which may be positioned over a selected fuel assembly in the reactor core. An extendable camera mast having a camera mounted thereon moves vertically with respect to a stationary camera mast and the refueling mast in order to allow for visual inspection of various components in the reactor core. The camera mast assembly preferably includes a video cable take-up mechanism for handling the camera video cable as the extendable camera mast is moved up and down. The camera mast assembly is preferably removably mounted on the refueling mast in order to aid in installation and removal. The removable mounting also allows the camera mast assembly to be used independently of the refueling mast. The camera mast assembly may optionally include an extendable fuel assembly guide mast including a guide member which facilitates placement of fuel assemblies within the reactor core.

5040287, Aug 20, 1991

Jun 19, 1989

7/368495

Robert E. Meuschke - Monroeville PA
Paul P. Pomaibo - North Huntingdon PA

The United States of America as represented by the United States
Department of Energy - Washington DC

B23P 1900

29723

A method for installing a heater unit assembly (52, 54) in a reactor pressure vessel (2) for performance of an annealing treatment on the vessel (2), the vessel (2) having a vertical axis, being open at the top, being provided at the top with a flange (6) having a horizontal surface, and being provided internally, at a location below the flange (6), with orientation elements (8) which are asymmetrical with respect to the vertical axis, by the steps of: providing an orientation fixture (10) having an upwardly extending guide member (18) and orientation elements (14, 16) and installing the orientation fixture (10) in the vessel (2) so that the orientation elements (14,16) of the orientation fixture (10) mate with the orientation elements (8) of the pressure vessel (2) in order to establish a defined position of the orientation fixture (10) in the pressure vessel (2), and so that the guide member (18) projects above the pressure vessel (2) flange (6); placing a seal ring (30) in a defined position on the pressure vessel (2) flange (6) with the aid of the guide member (18); mounting at least one vertical, upwardly extending guide stud (40) upon the seal ring (30); withdrawing the orientation fixture (10) from the pressure vessel (2); and moving the heater unit assembly (52,54) vertically downwardly into the pressure vessel (2) while guiding the heater unit assembly (52,54) along a path with the aid of the guide stud (40).

5225150, Jul 6, 1993

Jun 23, 1992

7/903250

Louis J. Malandra - McKeesport PA
Leonard P. Hornak - Forest Hills PA
Robert E. Meuschke - Monroeville PA

Westinghouse Electric Corp. - Pittsburgh PA

G21C 1900, G21C 1100

376263

A nuclear reactor such as a pressurized water reactor has an integrated head package providing structural support and increasing shielding leading toward the vessel head. A reactor vessel head engages the reactor vessel, and a control rod guide mechanism over the vessel head raises and lowers control rods in certain of the thimble tubes, traversing penetrations in the reactor vessel head, and being coupled to the control rods. An instrumentation tube structure includes instrumentation tubes with sensors movable into certain thimble tubes disposed in the fuel assemblies. Couplings for the sensors also traverse penetrations in the reactor vessel head. A shroud is attached over the reactor vessel head and encloses the control rod guide mechanism and at least a portion of the instrumentation tubes when retracted. The shroud forms a structural element of sufficient strength to support the vessel head, the control rod guide mechanism and the instrumentation tube structure, and includes radiation shielding material for limiting passage of radiation from retracted instrumentation tubes. The shroud is thicker at the bottom adjacent the vessel head, where the more irradiated lower ends of retracted sensors reside.

5384812, Jan 24, 1995

Mar 16, 1994

8/213891

Robert E. Meuschke - Monroeville PA
Daniel M. Trombola - Murrysville PA

Westinghouse Electric Corporation - Pittsburgh PA

G21C 1900

376260

A cabling arrangement is provided for a nuclear reactor located within a containment. Structure inside the containment is characterized by a wall having a near side surrounding the reactor vessel defining a cavity, an operating deck outside the cavity, a sub-space below the deck and on a far side of the wall spaced from the near side, and an operating area above the deck. The arrangement includes a movable frame supporting a plurality of cables extending through the frame, each connectable at a first end to a head package on the reactor vessel and each having a second end located in the sub-space. The frame is movable, with the cables, between a first position during normal operation of the reactor when the cables are connected to the head package, located outside the sub-space proximate the head package, and a second position during refueling when the cables are disconnected from the head package, located in the sub-space. In a preferred embodiment, the frame straddles the top of the wall in a substantially horizontal orientation in the first position, pivots about an end distal from the head package to a substantially vertically oriented intermediate position, and is guided, while remaining about vertically oriented, along a track in the sub-space to the second position.

5515407, May 7, 1996

Aug 25, 1994

8/295567

Bruce W. Bevilacqua - Export
Robert E. Meuschke - Monroeville PA
Edward J. Rusnica - Hempfield Township PA

Westinghouse Electric Corporation - Pittsburgh PA

G21C 1524

376372

A jet pump assembly for recirculating coolant through a recirculation loop of a boiling water reactor vessel, the jet pump assembly comprises a jet pump in operative association with the recirculation loop for forcing the coolant through the recirculation loop. A beam is positioned adjacent and in operative association with the jet pump for assisting in maintaining the positional relationship of the jet pump. A bolt is inserted in the beam for resisting the hydraulic forces generated in the jet pump, and an insert is disposed in said beam for receiving and surrounding the bolt which, in turn, reduces stress on the beam.

5442666, Aug 15, 1995

Mar 4, 1994

8/206306

Robert E. Meuschke - Monroeville PA
Thomas G. Bengel - Plum Borough PA
Frank I. Bauer - Perry Township PA
Phillip E. Miller - Greensburg PA

Westinghouse Electric Corporation - Pittsburgh PA

G21C 1906

376272

A tank is disclosed for containing a liquid in which control rod drive shafts of a nuclear power plant are stored. The tank comprises a lower tank portion having a bottom and a tank wall extending outwardly from the bottom for defining a lower storage cavity of the tank. An upper tank portion having walls is removably attached to the lower tank portion for defining an upper storage cavity of the tank. A plurality of tubes are arranged in the lower tank portion for adaptably receiving the shafts for storage.

5588031, Dec 24, 1996

Oct 27, 1994

8/330058

Bruce W. Bevilacqua - Export PA
Louis J. Malandra - McKeesport PA
Robert E. Meuschke - Monroeville PA
Alex W. Harkness - Gibsonia PA

Westinghouse Electric Corporation - Pittsburgh PA

G21C 900

376287

An apparatus, which reinforces a shroud that is contained within a reactor vessel, is operable for reinforcement of the shroud in the event of cracking in the shroud. The apparatus comprises a reactor wall positioned surrounding the shroud. A beam is attached to and extends generally axially on the shroud for absorbing the forces generated by the cracking in the shroud, and a radial support is positioned between the beam and the wall of the reactor vessel for transmitting any forces absorbed by the beam to the wall.

6266386, Jul 24, 2001

Oct 13, 1999

9/417350

Raman G. Patel - Pittsburgh PA
Robert E. Meuschke - Monroeville PA
Moshe A. Mahlab - Pittsburgh PA
David E. Boyle - Pittsburgh PA

Westinghouse Electric Company LLC - Pittsburgh PA

G21C 1902, G21C 1920

376260

An apparatus and method are provided for inverting the lower internal assembly of a nuclear reactor. The apparatus includes a frame which is sized to receive the lower internal assembly. The frame supports the lower internal assembly as it is being inverted. The apparatus also includes a spider assembly which fits within the lower internal assembly and provides support for a baffle assembly located therein. The method includes the steps of removing the lower internal assembly from a reactor vessel and rotating the lower internal assembly prior to performing maintenance.

5687207, Nov 11, 1997

Apr 2, 1996

8/627747

Robert E. Meuschke - Monroeville PA
Louis J. Malandra - McKeesport PA

Westinghouse Electric Corporation - Pittsburgh PA

G21C 1920

376264

A refueling machine for refueling a pressurized water reactor has a trolley which travels on rails mounted on a transversely movable bridge. The trolley supports a refueling mast which includes an outer mast and two horizontally spaced apart, vertically movable gripper masts disposed within the outer mast. This design permits the machine to safely handle two fuel assemblies simultaneously in order to substantially reduce refueling critical path time. The two gripper masts can be raised, lowered and otherwise operated independently of each other. A partition plate extending through the stationary mast between the two movable gripper masts permits each fuel assembly held in the refueling mast to be independently leak tested.