Gerald Wayne Potts

US Patent:

8116422, Feb 14, 2012

Filed:

Dec 29, 2005

Appl. No.:

11/320477

Inventors:

Daniel Reese Lutz - San Jose CA, US
Gerald Allen Potts - Wilmington NC, US
Yang-Pi Lin - Wilmington NC, US
Sheikh Tahir Mahmood - Pleasanton CA, US
Mark Andrew Dubecky - Wilmington NC, US
David William White - Wilmington NC, US
John Schardt - Wilmington NC, US

Assignee:

General Electric Company - Shenectady NY

International Classification:

G21C 9/00
G21C 7/10

US Classification:

376277, 376305, 376412

Abstract:

A zirconium alloy suitable for forming reactor components that exhibit reduced irradiation growth and improved corrosion resistance during operation of a light water reactor (LWR), for example, a boiling water reactor (BWR). During operation of the reactor, the reactor components will be exposed to a strong, and frequently asymmetrical, radiation fields sufficient to induce or accelerate corrosion of the irradiated alloy surfaces within the reactor core. Reactor components fabricated from the disclosed zirconium alloy will also tend to exhibit an improved tolerance for cold-working during fabrication of the component, thereby simplifying the fabrication of such components by reducing or eliminating subsequent thermal processing, for example, anneals, without unduly degrading the performance of the finished component.

US Patent:

20110180184, Jul 28, 2011

Filed:

Dec 15, 2006

Appl. No.:

11/611348

Inventors:

Daniel Reese Lutz - San Jose CA, US
Yang-Pi Lin - Wilmington NC, US
Gerald Potts - Wilmington NC, US
William H. Jackson - Castle Hayne NC, US

International Classification:

C23C 8/00
G21C 3/07
B23K 26/00

US Classification:

148241, 376412, 21912185

Abstract:

A method for treating a Zr-alloy fuel bundle material in a nuclear reactor includes treating a surface of the Zr-alloy fuel bundle material with a laser beam generated by a solid-state laser, and a nuclear reactor including a treated Zr-alloy fuel bundle material. This may reduce the generation of shadow corrosion and/or reduce the propensity for interference between control blade and fuel channel during operation of the nuclear reactor.

US Patent:

54377471, Aug 1, 1995

Filed:

Apr 23, 1993

Appl. No.:

8/052791

Inventors:

Ronald B. Adamson - Fremont CA
Gerald A. Potts - San Jose CA

Assignee:

General Electric Company - San Jose CA

International Classification:

C22F 118

US Classification:

148519

Abstract:

In a zirconium-alloy fuel element cladding, a method for generating regions of coarse and fine intermetallic precipitates across the cladding wall is provided. The method includes steps of specific heat treatments and anneals that coarsen precipitates in the bulk of the cladding. The method also includes at least one step in which an outer region (exterior) of the cladding is heated to the beta or alpha plus beta phase, while an inner region (interior) is maintained at a temperature at which little or no metallurgical change occurs. This method produces a composite cladding in which the outer region comprises fine precipitates and the inner region comprises coarse precipitates.

US Patent:

55197485, May 21, 1996

Filed:

Apr 23, 1993

Appl. No.:

8/052793

Inventors:

Ronald B. Adamson - Fremont CA
Gerald A. Potts - San Jose CA

Assignee:

General Electric Company - San Jose CA

International Classification:

G21C 307

US Classification:

376457

Abstract:

A Zircaloy cladding having an outer region comprising fine precipitates and inner region comprising coarse precipitates is provided. The outer region comprises about 10% and the inner region comprises about 90% of the cladding wall thickness. Such Zircaloy tubing is resistant to propagation of cracks and at the same time resistant to corrosion in boiling water reactors (BWR). Resistance to damage caused by the pellet-cladding-interaction can be achieved by standard application of a zirconium or zirconium-alloy liner on the tubing inside surface.

US Patent:

56183569, Apr 8, 1997

Filed:

Jun 12, 1995

Appl. No.:

8/489597

Inventors:

Ronald B. Adamson - Fremont CA
Gerald A. Potts - Wilmington NC

Assignee:

General Electric Company - Wilmington NC

International Classification:

C22F 118

US Classification:

148519

Abstract:

In a zirconium-alloy fuel element cladding, a method for generating regions of coarse and fine intermetallic precipitates across the cladding wall is provided. The method includes steps of specific heat treatments and anneals that coarsen precipitates in the bulk of the cladding. The method also includes at least one step in which an outer region (exterior) of the cladding is heated to the beta or alpha plus beta phase, while an inner region (interior) is maintained at a temperature at which little or no metallurgical change occurs. This method produces a composite cladding in which the outer region comprises fine precipitates and the inner region comprises coarse precipitates.

US Patent:

56814046, Oct 28, 1997

Filed:

Feb 9, 1995

Appl. No.:

8/385807

Inventors:

Ronald Bert Adamson - Fremont CA
Gerald Allen Potts - San Jose CA

Assignee:

General Electric Co., Wilmington Facility - Wilmington NC

International Classification:

C22F 118

US Classification:

148421

Abstract:

In a zirconium-alloy fuel element cladding, a method for generating regions of coarse and fine intermetallic precipitates across the cladding wall is provided. The method includes steps of specific heat treatments and anneals that coarsen precipitates in the bulk of the cladding. The method also includes at least one step in which an outer region (exterior) of the cladding is heated to the beta or alpha plus beta phase, while an inner region (interior) is maintained at a temperature at which little or no metallurgical change occurs. This method produces a composite cladding in which the outer region comprises fine precipitates and the inner region comprises coarse precipitates.