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.
Surface Laser Treatment Of Zr-Alloy Fuel Bundle Material
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.
Method Of Fabricating Zircalloy Tubing Having High Resistance To Crack Propagation
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.
Zircaloy Tubing Having High Resistance To Crack Propagation
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.
Method Of Fabricating Zircaloy Tubing Having High Resistance To Crack Propagation
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.
Method Of Fabricating Zircaloy Tubing Having High Resistance To Crack Propagation
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.
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Highlands Elementary School Edina MN 1978-1979, Creek Valley Elementary School Edina MN 1979-1981, Randels Elementary School Flint MI 1981-1984, Dye Junior High School Flint MI 1984-1986, Carman - Ainsworth Junior High School Flint MI 1986-1988
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