|6902634||Method for manufacturing zirconium-based alloys containing niobium for use in nuclear fuel rod cladding|
The present invention relates to a method for manufacturing zirconium-based alloys containing niobium with superior corrosion resistance for use in nuclear fuel rod claddings. The method of this invention comprises melting of the alloy, β-forging, β-quenching, hot...
|6811746||Zirconium alloy having excellent corrosion resistance and mechanical properties for nuclear fuel cladding tube|
The present invention relates to a zirconium alloy having excellent corrosion resistance and mechanical properties and a method for preparing a nuclear fuel cladding tube by zirconium alloy. More particulary, the present invention is directed to a zirconium alloy co...
|6813329||Crud-resistant nuclear fuel cladding|
A crud-resistant nuclear fuel element cladding in which the axial locations that experience nucleate boiling during reactor full power operation are highly polished so that the maximum size of any surface defect on the highly polished surface is approximately 0.1 mi...
|6512806||Component designed for use in a light water reactor, and a method for the manufacture of such a component|
A component (1) designed for use in a light water reactor and at least partly comprised by a metal and/or a metal alloy presents a coatings (4, 7) at its outer surface (3) and its inner surface(5). The coating (4 and 7 respectively) has as its task to pro...
|6125161||Method for making Zr alloy nuclear reactor fuel cladding having excellent corrosion resistance and creep properties|
The invention provides a method for making Zr alloy nuclear reactor fuel cladding having excellent corrosion resistance and creep properties. The method includes performing hot forging, solution heat treatment, hot extruding, and repeated cycles of anneal...
|4879093||Ductile irradiated zirconium alloy|
A stabilized alpha metal matrix provides an improved ductility after irradation without loss of corrosion resistance in a "Zircaloy" alloy modified with measurable amounts of up to 0.6 percent by weight of niobium or 0.1 percent by weight of molybdenum. T...
|4664881||Zirconium base fuel cladding resistant to PCI crack propagation|
The present invention pertains to zirconium base alloys containing about 0.1 to 0.6 weight percent tin; about 0.07 to 0.24 weight percent iron; about 0.05 to 0.15 weight percent chromium; and up to about 0.05 weight percent nickel. The balance of the allo...
|4302287||Nuclear reactor operation control process|
A method for controlling the operation of a nuclear reactor to increase the reactor power in a range in which pellet-clad-mechanical-interaction occurs. The method includes the steps of increasing the reactor power from a power level in which pellet-clad-...
|4077838||Pyrolytic carbon-coated nuclear fuel|
An improved nuclear fuel kernel having at least one pyrolytic carbon coating and a silicon carbon layer is provided in which extensive interaction of fission product lanthanides with the silicon carbon layer is avoided by providing sufficient UO2
A nuclear fuel particle wherein a core, up to about 250 microns in diameter, of a normally solid fissionable material is completely encased in a shell having at least two concentric layers. A yielding of carbonaceous material about 5 to about 50 microns t...
|3992258||Coated nuclear fuel particles and process for making the same|
An improved nuclear fuel particle comprises (a) a generally spherical low density kernel of a fissile element having a void volume of at least 40 percent of the physical volume of the kernel in order to accommodate fission gases generated during the use o...
|3940312||Nuclear fuel and process of preparation thereof|
Vanadium carbide is present in the particles as supersaturated solid solution and the particles are coated with a thin porous layer of vanadium carbide....