Daniel Demond 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:

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:

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:

20120033779, Feb 9, 2012

Filed:

Aug 4, 2010

Appl. No.:

12/850244

Inventors:

Daniel Reese Lutz - Sunol CA, US
Young Jin Kim - Clifton Park NY, US
Yang-Pi Lin - Wilmington NC, US

Assignee:

GLOBAL NUCLEAR FUEL - AMERICAS, LLC - Wilmington NC

International Classification:

G21C 17/00

US Classification:

376259

Abstract:

A method of determining in-reactor susceptibility of a zirconium-based alloy to shadow corrosion according to a non-limiting embodiment of the present invention may include immersing a first electrode and a second electrode in an electrolytic solution. The first electrode may be formed of the zirconium-based alloy, while the second electrode may be formed of a metallic material suitable for use in a nuclear reactor and having a higher electrochemical corrosion potential than the zirconium-based alloy. The method may additionally include irradiating the immersed first and second electrodes with electromagnetic radiation. A galvanic current may then be measured between the first electrode and the second electrode to ascertain the relative in-reactor susceptibility of the zirconium-based alloy to shadow corrosion. The present invention allows a simplified and more rapid method of developing solutions that mitigate shadow corrosion, thereby potentially saving years of expensive in-reactor testing.

US Patent:

54177804, May 23, 1995

Filed:

Oct 28, 1993

Appl. No.:

8/142034

Inventors:

Ronald B. Adamson - Fremont CA
Daniel R. Lutz - San Jose CA

Assignee:

General Electric Company - San Jose CA

International Classification:

C22C 1600

US Classification:

148520

Abstract:

A method for fabricating a composite cladding comprised of a moderate-purity metal barrier of zirconium metallurgically bonded on the inside surface of a zirconium alloy tube which improves corrosion resistance. The improved corrosion resistance of the liner is accomplished by suitable heat treatment of the Zircaloy-zirconium composite cladding to allow diffusion of alloying elements, notably Fe and Ni, from the Zircaloy into the zirconium, in particular, to the inner surface of the zirconium liner. This diffusion anneal reduces the undesirable tendency of zirconium liner to oxidize rapidly.