Daniel Reese Lutz

US Patent:

6542566, Apr 1, 2003

Filed:

Mar 7, 2001

Appl. No.:

09/801364

Inventors:

Ronald Bert Adamson - Fremont CA 94536
Daniel Reese Lutz - San Jose CA 95126
Mickey Orville Marlowe - Wilmington NC 28405
John Frederick Schardt - Wilmington NC 28403
Cedric David Williams - Wilmington NC 28409

International Classification:

G21C 300

US Classification:

376417, 376416, 376305

Abstract:

An improved fuel element for use in a nuclear reactor comprised of a central core of nuclear material, which is surrounded by a composite cladding. The cladding has an outer metallic tubular portion comprised of well-known cladding alloys used for such purposes. Metallurgically bonded to the outer metallic tubular portion is a commercially pure zirconium microalloyed with a controlled quantity of iron. The zirconium microalloyed with iron produced an inner metallic barrier having a beneficial balance between stress corrosion crack resistance and corrosion resistance while retaining other beneficial properties of pure zirconium, such as ductility.

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:

8565367, Oct 22, 2013

Filed:

Apr 8, 2008

Appl. No.:

12/078904

Inventors:

Daniel Reese Lutz - San Jose CA, US

Assignee:

Global Nuclear Fuel-Americas, LLC - Wilmington NC

International Classification:

G21C 3/34

US Classification:

376438, 376409, 376426, 376434

Abstract:

Example embodiments are directed to fuel assembly components and nuclear fuel bundles including the fuel assembly components. Example embodiments of a fuel assembly component may include a cylindrical device having first and second ends and a mounting assembly on the first end of the cylindrical device configured to attach to and detach from a partial length fuel rod. Example embodiments of a nuclear fuel bundle may include an upper tie plate, a lower tie plate, at least one full-length fuel rod, at least one partial length fuel rod, and a fuel assembly component.

US Patent:

8043448, Oct 25, 2011

Filed:

Sep 8, 2004

Appl. No.:

10/935156

Inventors:

David White - Wilmington NC, US
Daniel R. Lutz - San Jose CA, US
Yang-Pi Lin - Wilmington NC, US
John Schardt - Wilmington NC, US
Gerald Potts - Wilmington NC, US
Robert Elkins - Wilmington NC, US
Hiroaki Kagami - Kanagawa-Ken, JP
Hideyuki Mukai - Kanagawa-Ken, JP

Assignee:

Global Nuclear Fuel-Americas, LLC - Wilmington NC

International Classification:

C22F 1/18

US Classification:

148672, 148421, 376277

Abstract:

Disclosed herein are zirconium-based alloys that may be fabricated to form nuclear reactor components, particularly fuel cladding tubes, that exhibit sufficient corrosion resistance and hydrogen absorption characteristics, without requiring a late stage α+β or β-quenching processes. The zirconium-base alloys will include between about 1. 30-1. 60 wt % tin; 0. 0975-0. 15 wt % chromium; 0. 16-0. 24 wt % iron; and up to about 0. 08 wt % nickel, with the total content of the iron, chromium and nickel comprising at least about 0. 3175 wt % of the alloy. The resulting components will exhibit a surface region having a mean precipitate sizing of between about 50 and 100 nm and a Sigma A of less than about 2×10hour with the workpiece processing generally being limited to temperatures below 680 C. for extrusion and below 625 C. for all other operations, thereby simplifying the fabrication of the nuclear reactor components while providing corrosion resistance comparable with conventional alloys.

US Patent:

20060048870, Mar 9, 2006

Filed:

Sep 8, 2004

Appl. No.:

10/935157

Inventors:

David White - Wilmington NC, US
Daniel Lutz - San Jose CA, US
Yang-Pi Lin - Wilmington NC, US
John Schardt - Wilmington NC, US
Gerald Potts - Wilmington NC, US

International Classification:

C22F 1/18

US Classification:

148672000

Abstract:

Disclosed herein are zirconium-based alloys and methods of fabricating nuclear reactor components, particularly fuel cladding tubes, from such alloys that exhibit improved corrosion resistance in aggressive coolant compositions. The fabrication steps include a late-stage β-treatment on the outer region of the tubes. The zirconium-based alloys will include between about 1.30 and 1.60 wt % tin; between about 0.06 and 0.15 wt % chromium; between about 0.16 and 0.24 wt % iron, and between 0.05 and 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising above about .31 wt % of the alloy and will be characterized by second phase precipitates having an average size typically less than about 40 nm. The final finished cladding will have a surface roughness of less than about 0.50 μm Ra and preferably less then about 0.10 μm Ra.

US Patent:

20060203952, Sep 14, 2006

Filed:

Mar 14, 2005

Appl. No.:

11/079356

Inventors:

Samson Hettiarachchi - Menlo Park CA, US
Daniel Lutz - San Jose CA, US

International Classification:

G21C 9/00

US Classification:

376305000

Abstract:

A method of reducing hydrogen absorption in fuel assembly components fabricated from zirconium alloys in a nuclear reactor is provided. The method includes, in an exemplary embodiment, depositing at least one noble metal on at least one surface of the fuel assembly component. Depositing at least one noble metal includes exposing the zirconium alloy fuel assembly components, outside the nuclear reactor, to an aqueous solution including at least one compound containing at least one noble metal.

US Patent:

20100014624, Jan 21, 2010

Filed:

Jul 17, 2008

Appl. No.:

12/219212

Inventors:

Daniel R. Lutz - San Jose CA, US
Young Jin Kim - Clifton Park NY, US
Yang-Pi Lin - Wilmington NC, US

International Classification:

G21C 9/00
G21F 1/08

US Classification:

376305

Abstract:

Example embodiments are directed to providing a thin, adherent coating on the surfaces of nuclear reactor components, which are known to cause increased corrosion on adjacent zirconium alloy structures, and methods of reducing the increased corrosion. Example embodiments include coatings being structurally bonded to components such that the difference in the corrosion potential between a coated component and a zirconium alloy component is less than that between a component without the coating and the zirconium alloy component.

US Patent:

20110123388, May 26, 2011

Filed:

Nov 24, 2009

Appl. No.:

12/624845

Inventors:

Yang-Pi Lin - Wilmington NC, US
David W. White - Wilmington NC, US
Daniel R. Lutz - San Jose CA, US

International Classification:

C22C 16/00

US Classification:

420422

Abstract:

An alloy according to example embodiments of the present invention may include zirconium, tin, iron, chromium, and nickel, with a majority of the alloy being zirconium. The composition of the alloy may be about 0.85-2.00% tin by weight, about 0.15-0.30% iron by weight, about 0.40-0.75% chromium by weight, and less than 0.01% nickel by weight. The alloy may further include 0.004-0.020% silicon by weight, 0.004-0.020% carbon by weight, and/or 0.05-0.20% oxygen by weight. Accordingly, the alloy exhibits reduced hydrogen absorption and improved corrosion resistance and may be used to farm a fuel assembly component.