Anthony Lee Reese

US Patent:

6535568, Mar 18, 2003

Filed:

Oct 4, 2000

Appl. No.:

09/678665

Inventors:

Anthony P. Reese - Wilmington NC

Assignee:

Global Nuclear Fuel -- Americas LLC - Wilmington NC

International Classification:

G21C 1700

US Classification:

376245, 376255

Abstract:

A method and system for demonstrating compliance of nuclear fuel rods with fundamental licensing criteria for fuel rod internal pressure during nuclear reactor operation is presented. A nuclear fuel rod evaluation process is performed during the fuel cycle design and licensing process for each operating cycle of a particular nuclear reactor. The evaluation process includes a rod-by-rod internal pressure analysis based on empirical data of actual operational power output levels of each fuel rod in the reactor core. A computer program constructs individual fuel rod power histories for each nuclear fuel rod in the reactor core based on empirical information acquired during previous fuel cycles and the projected operation of the reactor in an upcoming fuel cycle. Using the constructed power histories for each fuel rod, the program then computes thermal and mechanical overpower limits and a maximum internal pressure for each rod in the upcoming fuel cycle. Licensing compliance is demonstrated by confirming that the computed maximum internal pressure and maximum thermal and mechanical overpower stresses of any fuel rod for the upcoming fuel cycle is less than the fundamental licensing limits.

US Patent:

20060146973, Jul 6, 2006

Filed:

Dec 30, 2004

Appl. No.:

11/024432

Inventors:

Harold Yeager - Wilmington NC, US
Russell Stachowski - Wilmington NC, US
Charles McNeely - Wilmington NC, US
Gerald Potts - Wilmington NC, US
Anthony Reese - Wilmington NC, US
Robert Rand - Wilmington NC, US
Robert Schneider - Wilmington NC, US

International Classification:

G21C 17/00

US Classification:

376251000

Abstract:

A system and method for assessing failure of fuel rods are disclosed. The method may include monitoring fuel rod operational conditions, comparing the fuel rod parameters to parameters limits, calculating the fuel rod performance parameters to determine the likelihood of failure of individual fuel rods, and updating plant operating parameters based on the calculated fuel rod parameters. The system may input the calculated fuel rod parameters into a fuel failure model to assess the probability of failure, and predict the probability of failure of individual fuel rods based on fuel rod parameters in the fuel failure model.

US Patent:

20110249785, Oct 13, 2011

Filed:

Apr 8, 2010

Appl. No.:

12/756236

Inventors:

Anthony P. REESE - Wilmington NC, US
Lukas Trosman - Wilmington NC, US

International Classification:

G21C 3/07
G21C 3/32
G21C 3/00

US Classification:

376419, 376409, 376434

Abstract:

Disclosed are a fuel rod and a fuel bundle using the fuel rod. The fuel rod may include first enriched uranium in a boost zone of the fuel rod, wherein the boost zone may be arranged directly at a bottom of the fuel rod. The fuel rod may also include second enriched uranium in a second zone of the fuel rod, wherein the second zone is arranged over the boost zone. The fuel rod may also include natural uranium in a third zone of the fuel rod, wherein the third zone is arranged over the second zone. In this fuel rod, a percent of enrichment of the enriched uranium in the boost zone is at least one percent.

US Patent:

62597566, Jul 10, 2001

Filed:

Aug 22, 2000

Appl. No.:

9/642929

Inventors:

Anthony Paul Reese - Wilmington NC
Harold Hartney Yeager - Wilmington NC

Assignee:

General Electric Company - Schenectady NY

International Classification:

G21C 708

US Classification:

376237

Abstract:

In a nuclear reactor core, control blades form discrete control blade groups forming a core pattern including first and second main groups, respectively, symmetrically and asymmetrically arranged about the core. Each main group has first and second sub-groups, each sub-group at each control blade location within the core being located alternately in orthogonally-related X and Y directions in plan view of the core. The first sub-group of the first main group includes an operational sub-group. The blades of the first and second main groups are used simultaneously. The blades of the second main group are used only as shallow blades. The blades of the first main group are movable into deep or shallow positions from withdrawn positions. Each fuel bundle operates without an adjacent control blade for a time period twice as long as any previous period of operation with an adjacent control blade inserted into the core. Any one control blade is fully withdrawn for two consecutive periods after insertion.

US Patent:

57270392, Mar 10, 1998

Filed:

Mar 19, 1996

Appl. No.:

8/616509

Inventors:

John L. Harmon - Wilmington NC
Richard G. Patterson - Wilmington NC
Robert B. Elkins - Wilmington NC
Russell P. Higgins - Wilmington NC
Edward A. Croteau - Mukwonago WI
Harold B. King - Wrightsville Beach NC
Christian D. Frederickson - Wilmington NC
Gerald M. Latter - Wilmington NC
Anthony P. Reese - Wilmington NC
David W. White - Wilmington NC

Assignee:

General Electric Company - Schenectady NY

International Classification:

G21C 334

US Classification:

376442

Abstract:

In a nuclear reactor fuel bundle assembly having a plurality of fuel rods and a non-round water rod extending between upper and lower tie plates, and having at least one fuel rod spacer located along the non-round water rod, an improvement which includes cooperating components on the fuel rod spacer and on the water rod for permitting movement of the spacer along the water rod to a desired axial location and for thereafter preventing further axial movement of the spacer in at least one of two opposite axial directions, the cooperating components including at least one spring on one of the spacer and the water rod.

US Patent:

52290689, Jul 20, 1993

Filed:

Jul 15, 1992

Appl. No.:

7/914389

Inventors:

Eric B. Johansson - Wrightsville Beach NC
Bruce Matzner - San Jose CA
Gary E. Dix - Saratoga CA
Richard A. Wolters - San Jose CA
Anthony P. Reese - San Jose CA

Assignee:

General Electric Company - San Jose CA

International Classification:

G21C 1500

US Classification:

376371

Abstract:

In a fuel bundle for use in the core of a boiling water nuclear reactor, part length rods having a tendency to reduce pressure drop are used in combination with spacers and spacer attached devices tending to restore pressure drop to improve critical power. The addition of the part length rods has the advantage of lowering the pressure drop. Attached devices substantially recapture the pressure drop. Exemplary spacer attached mechanisms for the recapture of pressure drop are set forth including vanes--preferably swirl vanes on the spacers, decreasing the spacer pitch to increase the total number of spacers in the upper two phase region of the fuel bundle, increasing the vertical height of the spacers, and increasing the thickness of the metal from which the spacers are constructed. Two classes of separation devices are disclosed for placement in the volume overlying the end of the partial length fuel rods. A first type of device fits to the end of the part length rods and is primarily intended for preventing water passing along the surface of the part length rod adjacent the end of the part length rod from entering the volume overlying the part length fuel rod.

US Patent:

61817627, Jan 30, 2001

Filed:

Apr 5, 1999

Appl. No.:

9/285676

Inventors:

Sten O. Akerlund - Wilmington NC
Robert A. Rand - Wilmington NC
Roland O. Jackson - Wilmington NC
Anthony P. Reese - Wilmington NC
Russell M. Fawcett - Wilmington NC
John F. Schardt - Wilmington NC
Robert B. Elkins - Wilmington NC
Peter J. Savoia - Wilmington NC
Cary L. Kunz - Wilmington NC
Russell E. Stachowski - Fremont CA

Assignee:

General Electric Company - Schenectady NY

International Classification:

G21C 332

US Classification:

376435

Abstract:

A nuclear fuel bundle has differential peak power limits for the edge or peripheral fuel rods and the interior fuel rods. Also, the magnitude of nuclear fuel in the edge or peripheral rods is decreased in comparison with the magnitude of nuclear fuel in the interior rods. The nuclear reactor can thus operate at higher power output by decreasing the margins between the power outputs and peak power limit of the interior rods, as well as by decreasing the margins between the power outputs of the edge or peripheral rods and the increased peak power limit of those rods. The outer or peripheral edge rods can also be enriched for enhanced power output.