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Fred C Nopwaskey

from San Jose, CA
Age ~64
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Also known as:
Fred Charles Nopwaskey, Fred Te Nopwaskey, Fred C Nopwasky
Phone and address:
755 Promenade Ln, San Jose, CA 95138
(408) 839-1370
Related to:
Richard D Williams, 78Lloyd Fajardo, 65Leslie Ronquillo, 69Helen Fajardo, 73Judy Campanilla, 66Marlo Fajardo
Connected to:
Barbara K Nopwasky, 63Amira A Nor, 48Azman A Nor, 44Azura A Nor, 41Nabil F Nor, 58Noor A Nor, 53Shukri A Nor, 47Christina M Nora, 48David A Nora, 37Guadalupe A Nora, 64

Fred Nopwaskey Phones & Addresses

  • 755 Promenade Ln, San Jose, CA 95138 (408) 839-1370 (408) 360-9107
  • Corvallis, OR
  • Painesville, OH
  • Morgan Hill, CA
  • 755 Promenade Ln, San Jose, CA 95138

Work

Company: Orbotech Jun 2018 Position: Mechanical design engineer

Education

Degree: Bachelor of Science In Mechanical Engineering, Bachelors School / High School: West Virginia University 1979 to 1982 Specialities: Mechanical Engineering

Skills

Engineering • Nuclear • Mechanical Engineering • Engineering Management • Nuclear Engineering • Energy • Finite Element Analysis • Power Generation • Project Engineering • Process Engineering • Power Plants • Manufacturing • Root Cause Analysis • Solidworks • Project Management • Reactor • Mechanical Product Design • Remote Operated Equipment • Mechanical Design • Autodesk Inventor • Sheetmetal Design • Rapid Prototyping • Manufacturing Drawings • Manufacturing Modeling • Product Design

Interests

Science and Technology • Environment

Industries

Oil & Energy

Resumes

Resumes

Fred Nopwaskey Photo 1

Mechanical Engineer

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Location:
San Francisco, CA
Industry:
Oil & Energy
Work:
Orbotech
Mechanical Design Engineer
Water For Humans
Volunteer, Cad Designer
Ge Feb 2015 - Apr 2016
Mechanical Design Engineer
Areva Np Jul 2008 - Dec 2014
Advisory Engineer
Ge 2004 - 2008
Senior Engineer
Education:
West Virginia University 1979 - 1982
Bachelor of Science In Mechanical Engineering, Bachelors, Mechanical Engineering
Skills:
Engineering
Nuclear
Mechanical Engineering
Engineering Management
Nuclear Engineering
Energy
Finite Element Analysis
Power Generation
Project Engineering
Process Engineering
Power Plants
Manufacturing
Root Cause Analysis
Solidworks
Project Management
Reactor
Mechanical Product Design
Remote Operated Equipment
Mechanical Design
Autodesk Inventor
Sheetmetal Design
Rapid Prototyping
Manufacturing Drawings
Manufacturing Modeling
Product Design
Interests:
Science and Technology
Environment

Publications

Us Patents

Floor Mounted Ultra High Pressure Abrasive Cutting Apparatus

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US Patent:
6402587, Jun 11, 2002
Filed:
Dec 22, 1999
Appl. No.:
09/471051
Inventors:
Fred Charles Nopwaskey - San Jose CA
Hsueh-Wen Pao - Saratoga CA
Gary Allen Boortz - San Jose CA
Assignee:
General Electric Company - Schenectady NY
International Classification:
B24C 332
US Classification:
451 2, 451 76, 451 92
Abstract:
An ultra high pressure abrasive waterjet cutting apparatus for underwater cutting of structural components of a nuclear reactor is described. The cutting apparatus includes a multi-axis manipulator, an ultra high pressure abrasive waterjet (UHP) cutting nozzle coupled to the manipulator, a collection stand assembly, a collection hood movably coupled to the collection stand assembly, and a turntable having a non-movable center portion. The multi-axis manipulator is configured to mount on the non-movable center portion of the turntable or on the floor of the pool of water in which the structural component is positioned for cutting. The collection stand assembly is configured to mount on at least one of the floor and the wall of the pool of water. The cutting nozzle and collection hood are positioned on opposite sides of the structural component to be cut.

Ultra High Pressure Abrasive Waterjet Cutting Apparatus

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US Patent:
6533640, Mar 18, 2003
Filed:
Dec 14, 1999
Appl. No.:
09/461500
Inventors:
Fred Charles Nopwaskey - San Jose CA
Hsueh-Wen Pao - Saratoga CA
Gary Allen Boortz - San Jose CA
Assignee:
General Electric Company - Schenectady NY
International Classification:
B24C 300
US Classification:
451 2, 451 24, 451 27, 451 36, 451 38, 451 76
Abstract:
An ultra high pressure abrasive waterjet cutting apparatus for cutting nuclear reactor structural components is described. The cutting apparatus includes an ultra high pressure abrasive waterjet (UHP) cutting nozzle, movably coupled to a single axis manipulator, and a collection hood. The manipulator and the collection hood are coupled to a support frame and are configured to be positioned inside adjacent openings of a nuclear reactor top guide or core plate so that the cutting nozzle is in alignment with the collection hood. The manipulator includes a linear frame, a nozzle support plate movably coupled to the linear frame, and a motor operatively coupled to the nozzle support plate. The collection hood includes an elongate collection chamber having an elongate opening located so that the opening is in alignment with the cutting nozzle. The collection hood also includes at least one positioning cylinder coupled to the collection chamber and to the support frame which positions the collection chamber opening adjacent a top guide or core plate beam. The collection hood further includes an outlet port configured to be connected to a water filtration system.

Methods And Apparatuses For Operating And Repairing Nuclear Reactors

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US Patent:
8565366, Oct 22, 2013
Filed:
Apr 9, 2007
Appl. No.:
11/783365
Inventors:
Fred Charles Nopwaskey - San Jose CA, US
Ke Ling Lee - Cupertino CA, US
Alfred Wilhelm Dalcher - Los Gatos CA, US
Assignee:
General Electric Company - Schenectady NY
International Classification:
G21C 9/00
US Classification:
376285, 376286, 376249, 376277
Abstract:
Method of repairing nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: removing a damaged section of one of the one or more submerged lines; and replacing the damaged section of the one of the one or more submerged lines without welding. Methods of operating nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: shutting down the nuclear reactor; repairing damage to at least one of the one or more submerged lines without welding; and starting up the nuclear reactor. Methods of operating nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: cooling down the nuclear reactor; repairing damage to at least one of the one or more submerged lines without welding; and heating up the nuclear reactor.

Core Plate Lifting Fixture And Related Process

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US Patent:
61865680, Feb 13, 2001
Filed:
Jun 18, 1999
Appl. No.:
9/335695
Inventors:
Bettadapur N. Sridhar - Cupertino CA
Fred C. Nopwaskey - San Jose CA
Stephen K. Parker - Fremont CA
Frank C. Falzone - Santa Clara CA
Assignee:
General Electric Company - Schenectady NY
International Classification:
B66C 166
US Classification:
294 93
Abstract:
A lifting fixture includes a housing; a plurality of jaws movable radially in and out of the housing to secure the fixture to a component to be lifted; at least one lifting bail extending from on end of the housing; and a screw mechanism operatively connected to the plurality of jaws for moving the jaws radially between an inward retracted position and an outward locking position. A related lifting and flipping process is also disclosed.

Bwr Control Rod Handling Tooling & Method

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US Patent:
53772393, Dec 27, 1994
Filed:
Aug 18, 1993
Appl. No.:
8/108463
Inventors:
Fred C. Nopwaskey - Morgan Hill CA
Robert W. Whitling - Morgan Hill CA
Balasubramanian S. Kowdley - San Jose CA
Frank Ortega - San Jose CA
Assignee:
General Electric Company - San Jose CA
International Classification:
G21C 1910
US Classification:
376260
Abstract:
A tool set and a method of using those tools in combination is disclosed that are especially well adapted to the function of rearranging and/or replacing the control rods and fuel supports in a boiling water reactor. The tool set includes a grapple that is capable of simultaneously picking up both a control rod and its associated fuel support. A separate unlatching tool is provided for pulling the control rod's release handle in order to decouple the control rod from a control rod drive. A storage rack that may be mounted in the reactor pressure vessel is provided for storing a fuel support and a pair of control rods when the positions of selected control rods are being shifted about the reactor core area. In the method aspect of the invention, the unlatching tool is used to pull the control rod's release handle. Thereafter, the grapple lifts the control rod and its associated fuel support as a unit.
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Fred C Nopwaskey from San Jose, CA, age ~64 Get Report