Harry Andrews, Age 29119 Birmingham Ave, Pittsburgh, PA 15210

4270258, Jun 2, 1981

Dec 28, 1978

5/974161

Harry N. Andrews - Export PA
Edmund C. Eglinton - St. Petersburg FL
Joseph W. Gulaskey - N. Huntingdon PA
Leonard J. Balog - Pittsburgh PA
Robert W. Beer - Murrysville PA

Westinghouse Electric Corp. - Pittsburgh PA

B23P 700

291574

A method of rapidly retubing a steam generator while it is vertically oriented in a containment vessel and keeping the level of radiation to which workmen are subjected at a minimal level.

3940311, Feb 24, 1976

Jul 9, 1973

5/377846

Erling Frisch - LATE OF Pittsburgh PA
Harry N. Andrews - Export PA

Westinghouse Electric Corporation - Pittsburgh PA

G21c 708

176 36R

A system is provided for determining during operation of a nuclear reactor having fluid pressure operated control rod mechanisms the exact location of a fuel assembly with a defective fuel rod. The construction of the reactor internals is simplified in a manner to facilitate the testing for defective fuel rods and to reduce the cost of producing the upper internals of the reactor.

4941577, Jul 17, 1990

Jul 21, 1988

7/222584

Herbert E. Ferree - Greensburg PA
Harry N. Andrews - Export PA
Frank W. Cooper - Monroeville Borough PA
Joseph R. Herberg - Monroeville Borough PA

Space Industries Partnership, L.P. - Webster TX

A47F 700

211 706

A rack for holding a plurality of tools includes a plate member having openings for receiving tools, detent pins for releasably securing the plate member to a surface, detent clips associated with each opening for releasably securing a tool within the associated opening and pin members associated with each opening for interacting with a tool using device to permit engagement and disengagement of the tool to the tool using device.

4173997, Nov 13, 1979

Feb 23, 1977

5/771140

Harry N. Andrews - Export PA
Robert F. Barry - St. Genese, BE

Westinghouse Electric Corp. - Pittsburgh PA

F28F 300

165158

Modular bundles of U-shaped tubes having primary fluid conduits with compression seals which cooperate with a pair of transversely disposed parallel support plates to allow removal and replacement of the modular tube bundles to facilitate maintenance and extend steam generator life in pressurized water reactors.

5018901, May 28, 1991

Jul 21, 1988

7/222583

Herbert E. Ferree - Greensburg PA
Harry N. Andrews - Export PA
Frank W. Cooper - Monroeville Borough PA
Joseph R. Herberg - Monroeville Borough PA

Space Industries Partnership, L. P. - Webster TX

F16B 720

403349

A ring latched coupler includes a male assembly having a plurality of grooves and a female assembly having a plurality of slots. The female assembly is configured to receive the male assembly. A latching ring is rotatably carried by the female assembly. The latching ring is configured such that upon rotation of the male and female assemblies relative to the latching ring, portions of the latching ring extend through the slots in the female assembly to engage grooves in the male assembly.

4586079, Apr 29, 1986

Oct 7, 1983

6/540454

Frank W. Cooper - Monroeville PA
Harry N. Andrews - Murrysville PA
Matthew J. Randazzo - Tonawanda NY

Westinghouse Electric Corp. - Pittsburgh PA

H04N 718

358100

A fiberscope inspection system for a nuclear steam generating plant includes an optical unit and a transport unit respectively coupled to opposite ends of the fiberoptic cable and mounted at spaced-apart points on a trolley beneath the tube sheet, with the fiberoptic cable hanging freely in a catenary between the two units, both of which are coupled by cable to a remote control station. The optical unit is self-contained and includes a light source, a video camera and a focusing mechanism and chain and sprocket remotely-controlled drive means for controlling the focusing mechanism. The transport unit includes a cartridge comprising a coil of a steel drive tape, the leading end of which is welded to a split-sleeve coupling disposed in clamping engagement with the leading end of the fiberoptic cable, the tape being engageable by a drive sprocket for driving same to feed and retract the fiberoptic cable. Position sensing means are provided for monitoring the position of the fiberscope probe.

RE30247, Apr 1, 1980

Jun 25, 1975

5/590163

Harry N. Andrews - Murrysville PA
Herbert W. Keller - Monroeville PA

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

G21C 330

176 78

5. A grid structure for a nuclear reactor fuel assembly comprising a plurality of connecting members forming. [. at least one. ]. longitudinally extending. [. opening. ]. . Iadd. peripheral and inner fuel element openings. Iaddend. through. Iadd. each of. Iaddend. which. Iadd. openings. Iaddend. at least one nuclear fuel element extends, said connecting members forming wall means surrounding. [. said. ]. . Iadd. each peripheral and inner fuel element. Iaddend. opening, a pair of rigid projections. Badd. longitudinally spaced from one another. Baddend. extending from a portion of said wall means into. [. said. ]. . Iadd. each peripheral and inner. Iaddend. opening for rigidly engaging. [. said. ]. . Iadd. each. Iaddend. fuel element,. Iadd. respectively, yet permit individual longitudinal slippage thereof,. Iaddend.

4071403, Jan 31, 1978

Aug 1, 1974

5/493995

Harry N. Andrews - Export PA
Walter G. Roman - Pittsburgh PA

Westinghouse Electric Corporation - Pittsburgh PA

G21C 900

176 50

A method and apparatus for protecting fuel rods in a nuclear reactor core under conditions of a major break in the coolant inlet piping connected to the reactor inlet nozzle. A multi-venturi protector which includes multiple parallel dislosed venturies is mounted in the inlet nozzle. The characteristics of the venturi protector are such that coolant flow through the protector into the reactor is unimpeded, but reverse flow through the protector is restricted when a break occurs in the inlet piping. The resistance offered to such reverse flow permits reactor coolant and emergency core coolant to remain in contact with the reactor core for a time sufficient to allow the fuel rods to decrease in temperature to a low safe level.