Mark J Colby

US Patent:

20020161594, Oct 31, 2002

Filed:

Apr 27, 2001

Appl. No.:

09/842785

Inventors:

Helen Bryan - Wilmington NC, US
Mark Colby - Wilmington NC, US
Ralph Reda - Wilmington NC, US
Daniel Waltermire - Painesville OH, US
William Williams - Wilmington NC, US

International Classification:

G06F017/60

US Classification:

705/001000

Abstract:

A system for auditing complex systems, such as nuclear power plants, is disclosed. The system stores all documents necessary for an audit. These documents are available for remote review by auditors via an Internet website. The website has one or more graphical maps of the system, its components and/or sub-systems that allows the auditor to select and access documents in the database(s).

US Patent:

20040096026, May 20, 2004

Filed:

Nov 18, 2002

Appl. No.:

10/065772

Inventors:

Hwang Choe - Saratoga CA, US
Jose Casillas - Cupertino CA, US
Sig Wolf - Sunnyvale CA, US
Mark Colby - Wilmington NC, US

International Classification:

G21C019/28
G21C015/00

US Classification:

376/373000

Abstract:

A nuclear reactor core is provided that includes a plurality of fuel assemblies. In an exemplary embodiment, each fuel assembly includes a main coolant flow channel having an inlet. The plurality of fuel assemblies are arranged into at least three regions within the core. The flow channels are configured so that the flow of coolant through the main coolant flow channels of the fuel assemblies located in a particular region are substantially the same, and that the coolant flow through the fuel assemblies in each region is different from the coolant flow through the fuel assemblies in each other region.

US Patent:

57486956, May 5, 1998

Filed:

Nov 7, 1995

Appl. No.:

8/551769

Inventors:

Thomas G. Dunlap - Wilmington NC
Robert B. Elkins - Wilmington NC
Mark J. Colby - Wilmington NC

Assignee:

General Electric Company - Schenectady NY

International Classification:

G21C 3322

US Classification:

376446

Abstract:

A latch pin assembly is configured to enable selective engagement with at least one of the fuel assembly channel and the coolant rod such that the fuel assembly channel and the coolant rod can be selectively utilized to support the fuel assembly load, thereby eliminating the need for fuel tie rods. The latch pin assembly includes a latch pin selectively engageable with the fuel assembly channel and the coolant rod, and an anchoring assembly cooperating with the latch pin, wherein the anchoring assembly anchors the latch pin in a selected position such that the latch pin engages at least one of the fuel assembly channel and the coolant rod. The latch pin may be alternatively engageable with the fuel assembly channel and the coolant rod or simultaneously engageable with the fuel assembly channel and the coolant rod. With this arrangement, the bail handle can be used both to remove the entire assembly including the fuel assembly channel from the reactor vessel or to remove only the fuel bundle from the reactor vessel, leaving the fuel assembly channel in place.

US Patent:

47675950, Aug 30, 1988

Filed:

May 15, 1987

Appl. No.:

7/049897

Inventors:

Richard A. Wolters - San Jose CA
Mark J. Colby - San Jose CA
Robert B. Elkins - San Jose CA

Assignee:

General Electric Company - San Jose CA

International Classification:

G21C 1500
G21C 700

US Classification:

376353

Abstract:

In a boiling water reactor (BWR) of the D-lattice type an improved apparatus and method for the mounting of a nuclear fuel assembly is disclosed. Specifically, a D-lattice nuclear fuel assembly is diagonally displaced at the top and diagonally displaced at the bottom to and toward the cruciform shaped control rod interstices. Displacement at the bottom end of the nuclear fuel assembly occurs by an eccentrically centered lower tie plate and fluid inlet for fitting to the core plate at the bottom end of the assembly. Displacement at the top end of the nuclear fuel assembly occurs by shims in the vicinity of the upper end of the channel at the top guides. The disclosed channel assembly is capable of installation during refueling cycles, with a displaced channel being substituted for prior art conventional D-lattice channels. Substitution of one displaced channel occurs with each refueling cycle in a group of four channels. Consequently, there results at the end a maximum of four refueling cycles, complete installation of the displaced channels.

US Patent:

58091017, Sep 15, 1998

Filed:

May 29, 1996

Appl. No.:

8/655875

Inventors:

Thomas G. Dunlap - Wilmington NC
Gerald M. Latter - Wilmington NC
Mark J. Colby - Wilmington NC
Michael R. Stepp - Wilmington NC

Assignee:

General Electric Company - Schenectady NY

International Classification:

G21C 332

US Classification:

376446

Abstract:

A fuel bundle assembly for a nuclear reactor includes a modified channel and a handle unit that improves pressure drop performance. With the modified channel, one approach is to vary the outside dimension of the fuel channel along the length of the channel, but maintain a constant channel wall thickness. Another approach is to maintain the external dimensions of the fuel channel and vary the wall thickness along the length of the channel. The handle unit is formed including a handle member and a separate rod support member releasably engageable with the handle member. The handle member includes channels for receiving latch pin assemblies, coolant rods and a spacer assembly. The rod support member includes a plurality of fuel rod support chambers providing lateral support for the fuel rods of the fuel assembly. The rod support member also includes a main chamber that is sized to receive a portion of the handle member in a friction fit. In addition to providing improved pressure drop performance, the arrangement eliminates the need to realign the fuel rods in an upper tie plate or an upper spacer when access to the fuel rods is necessary.

US Patent:

57871400, Jul 28, 1998

Filed:

May 29, 1996

Appl. No.:

8/654957

Inventors:

Thomas G. Dunlap - Wilmington NC
Gerald M. Latter - Wilmington NC
Mark J. Colby - Wilmington NC
Michael R. Stepp - Wilmington NC

Assignee:

General Electric Company - Schenectady NY

International Classification:

G21C 332

US Classification:

376313

Abstract:

A fuel bundle assembly for a nuclear reactor includes a modified channel that improves pressure drop performance and a handle assembly that includes structure for preventing a broken end plug from escaping the fuel bundle. In modifying the channel, one approach is to vary the outside dimension of the fuel channel along the length of the channel, but maintain a constant channel wall thickness. Another approach is to maintain the external dimensions of the fuel channel and vary the wall thickness along the length of the channel. The handle assembly replaces the conventional upper tie plate and is provided with structure for preventing debris such as a broken fuel rod end plug from escaping the fuel bundle. The structure preferably includes a plurality of gridwork cross members forming a substantially square grid including gridwork windows that are sized smaller than the fuel rod end plugs.

US Patent:

50173324, May 21, 1991

Filed:

Jul 3, 1989

Appl. No.:

7/375646

Inventors:

Gary E. Dix - Saratoga CA
Russell L. Crowther - Saratoga CA
Mark J. Colby - San Jose CA
Bruce Matzner - San Jose CA
Robert B. Elkins - San Jose CA

Assignee:

General Electric Company - San Jose CA

International Classification:

G21C 1500

US Classification:

376370

Abstract:

In a boiling water reactor having discrete bundles of fuel rods confined within channel enclosed fuel assemblies, an improved fuel design of bundles of fuel rods interior of the channels is disclosed. Specifically, partial length rods are utilized which extend from the bottom of the channel only part way to the top of the channel. These partial length rods are shortened with respect to the remaining rods and are symmetrically distributed throughout the fuel bundle with the preferred disposition being in the second row of the bundle of fuel rods from the channel wall. The symmetrical distribution of the partial length rods is at spaced apart locations one from another. The partial length rods extend from the bottom of the fuel bundle and terminate within the boiling region. during shutdown of the reactor, an improved cold shutdown margin is produced at the top of the fuel assembly due to the improved moderator-to-fuel ratio and reduction in plutonium formation at the upper portion of the bundle. Shutdown control rod worth is improved due to greater moderator-to-fuel ratio and a longer thermal neutron diffusion length.

US Patent:

51125706, May 12, 1992

Filed:

Apr 4, 1988

Appl. No.:

7/176975

Inventors:

Gary E. Dix - Saratoga CA
Russell L. Crowther - Saratoga CA
Mark J. Colby - San Jose CA
Bruce Matzner - San Jose CA
Robert B. Elkins - San Jose CA

Assignee:

Hewlett-Packard Company

International Classification:

G21C 1500

US Classification:

376370

Abstract:

In a boiling water reactor having discrete bundles of fuel rods confined within channel enclosed fuel assemblies, an improved fuel design of bundles of fuel rods interior of the channels is disclosed. Specifically, partial length rods are utilized which extend from the bottom of the channel only part way to the top of the channel. These partial length rods are symmetrically distributed throughout the fuel bundle with the preferred disposition being in the second row of the bundle of fuel rods from the channel wall. The symmetrical distribution of the partial length rods is at spaced apart locations one from another. During shutdown of the reactor, an improved cold shutdown margin is produced at the top of the fuel assembly due to the improved moderator-to-fuel ratio and reduction in plutonium formation at the upper portion of the bundle. Shutdown control rod worth is improved due to greater moderator-to-fuel ratio and a longer thermal neutron diffusion length. During power reactor operation, the partial length fuel rods improve flow distributions above the ends of the partial length rods by channeling steam in the open interstitial area between rods above the ends of the partial length rods.