Leonard R Golick

US Patent:

49951580, Feb 26, 1991

Filed:

Feb 8, 1989

Appl. No.:

7/308271

Inventors:

David A. Howell - Plum Boro PA
Jeffrey E. Hydeman - Murrysville PA
Jeffrey L. Slater - Munhall PA
Richard J. Bodnar - Monroeville PA
Leonard R. Golick - Trafford PA
Robert S. Sekera - Monroeville PA
Charles H. Roth - N. Huntingdon PA

Assignee:

Westinghouse Electric Corp. - Pittsburgh PA

International Classification:

B23P 1900

US Classification:

29723

Abstract:

Process and apparatus are disclosed for removing and replacing the hold down beams of fluid circulating jet pumps mounted in a nuclear reactor. The disclosed process and apparatus are operable from a position such as the refueling bridge remote from the reactor and while the refueling cavity surrounding the reactor is flooded with moderator fluid.

US Patent:

43250262, Apr 13, 1982

Filed:

Mar 19, 1979

Appl. No.:

6/021652

Inventors:

Frank W. Cooper - Monroeville PA
Leonard R. Golick - Trafford PA

Assignee:

Westinghouse Electric Corp. - Pittsburgh PA

International Classification:

G01R 3312
G01N 2790

US Classification:

324232

Abstract:

An eddy current probe for mapping holes within a tube sheet of a steam generator, having a first coil (12) positioned at the top of the probe (10) with its axis coincident with the axis of the probe. A first coil pair (14 and 16) is arranged along a common axis perpendicular to the axis of the probe below the first coil (12) and is situated a distance from and on either side of the axis of the probe. A second pair of eddy current coils (18 and 20) is positioned along a common axis perpendicular to the axis of the probe and the axis of the first coil pair with the respective coils of the second pair located on either side of and spaced from the probe axis. Each of the respective coils are arranged to be separately excited by an alternating current source with the respective coil pairs coupled in opposition in corresponding balanced bridge arrangements. Means are provided for indicating a variation in the impedance of the first coil and an imbalance in either of the separate bridge arrangements of the first and second coil pairs.

US Patent:

48594091, Aug 22, 1989

Filed:

May 27, 1988

Appl. No.:

7/199416

Inventors:

John M. Matusz - Plum Boro PA
Leonard R. Golick - Trafford PA
Walter Matusz - North Braddock Boro PA

Assignee:

Westinghouse Electric Corp. - Pittsburgh PA

International Classification:

G21C 1900

US Classification:

376463

Abstract:

A temporary support structure for supporting a lower internals assembly above the reactor vessel during inspection and/or maintenance thereof. A support bracket is bolted to the reactor vessel flange at the vessel head stud closure holes. A pivotally mounted arm, upon the top surface of which the internals rest, is attached at one end to the support bracket and projects radially inwardly therefrom. A compliant foot depends from the bottom of the opposite end of the arm and engages the vessel internals support ledge to provide a secure support structure for the internals assembly. An alignment bracket on the arm aligns the internals with the support. Four such structures are installed around the circumference of the vessel flange while the internals are within the reactor vessel. The structure allows the lower internals to be quickly removed from the interior of the reactor vessel and placed on the temporary supports. By supporting the internals above the vessel from the vessel flange, the lower internals remain essentially completely submerged by the shielding medium.

US Patent:

50705890, Dec 10, 1991

Filed:

Oct 31, 1990

Appl. No.:

7/608061

Inventors:

David A. Howell - Plum Boro PA
Jeffrey E. Hydeman - Murrysville PA
Jeffrey L. Slater - Munhall PA
Richard J. Bodnar - Monroeville PA
Leonard R. Golick - Trafford PA
Robert S. Sekera - Monroeville PA
Charles H. Roth - N. Huntingdon PA

Assignee:

Westinghouse Electric Corp. - Pittsburgh PA

International Classification:

B23P 1902
B23Q 300

US Classification:

294265

Abstract:

Process and apparatus are disclosed for removing and replacing the hold down beams of fluid circulating jet pumps mounted in a nuclear reactor. The disclosed process and apparatus are operable from a position such as the refueling bridge remote from the reactor and while the refueling cavity surrounding the reactor is flooded with moderator fluid.

US Patent:

47434236, May 10, 1988

Filed:

Sep 28, 1984

Appl. No.:

6/655953

Inventors:

Robert L. Turner - Reston VA
Kimchinh Tran - Pittsburgh PA
Stephan L. Abbott - Monroeville PA
Leonard R. Golick - Trafford PA
David E. Boyle - Kiski Township, Armstrong County PA
Theodore A. Meyer - Penn Township, Westmoreland County PA

Assignee:

Westinghouse Electric Corp. - Pittsburgh PA

International Classification:

G21C 1100

US Classification:

376287

Abstract:

A shield panel for use in a nuclear reactor including a reactor vessel susceptible to embrittlement when bombarded with high energy neutrons and a nuclear reactor core mounted within the reactor vessel, the reactor vessel having a longitudinal axis and an inner surface surrounding the longitudinal axis, and the nuclear core emitting high energy neutrons which impinge on the inner surface of the reactor vessel. The shield panel includes a canister which contains a completely enclosed interior space and which is mountable between the inner surface of the reactor vessel and the nuclear core in a region wherein the reactor vessel is susceptible to a higher rate of embrittlement than the remaining portion of the vessel when bombarded with high energy neutrons emitted from the nuclear core, and a substance consisting essentially of a heavy metal and hydrogen filling the interior space of the canister.