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Ceramic reinforced zirconium alloy nuclear fuel cladding with intermediate oxidation resistant layer

A technology of nuclear fuel and cladding, which is applied to the problems related to rod cladding. It can be reinforced by SiC by winding or weaving, which can solve problems such as problems.

Inactive Publication Date: 2016-11-09
WESTINGHOUSE ELECTRIC CORP
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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  • Ceramic reinforced zirconium alloy nuclear fuel cladding with intermediate oxidation resistant layer
  • Ceramic reinforced zirconium alloy nuclear fuel cladding with intermediate oxidation resistant layer
  • Ceramic reinforced zirconium alloy nuclear fuel cladding with intermediate oxidation resistant layer

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Embodiment Construction

[0028] The present invention relates generally to fuel rod cladding, depositing a composition on the outer surface of the cladding to form a coating thereon, and a method of making a zirconium alloy nuclear fuel cladding having a Normal and accident condition capability. In certain embodiments, enclosures made in accordance with the present invention are capable of withstanding temperatures ranging from about 800°C to about 1200°C. In addition, the cladding is capable of withstanding beyond design basis accidents in nuclear water reactors.

[0029] Typically, the present invention involves depositing an anti-oxidant material, for example directly on the inner and / or outer surfaces of the cladding, to form a first inner and / or outer coating, respectively, and subsequently applying the first outer coating A SiC composition such as a composite is deposited thereon to form a second outer coating thereon.

[0030] The enclosure can be composed and constructed of a variety of conv...

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Abstract

The invention relates to compositions and methods for coating a zirconium alloy, e.g., ceramic-containing, cladding tube for use with fuel rods in a nuclear water reactor. The coating includes an intermediate oxidation resistant layer and a SiC containing layer at least partially deposited on the intermediate oxidation resistant layer. The SiC containing layer can include a plurality of fibers. The invention provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions to which it is exposed in the nuclear water reactor.

Description

[0001] Government support and funding [0002] This invention was made with government support under Grant #DE-NE0000566 awarded by the Department of Energy. The government has certain rights in this invention. Background technique [0003] The present invention relates to a method of making a zirconium alloy cladding for use in a nuclear water reactor, the cladding having a ceramic-containing coating formed thereon, the coating including an anti-oxidation layer, and in particular to a zirconium alloy cladding The ability of the shell to withstand improvements in the normal and accident conditions to which it is exposed in a nuclear water reactor. [0004] Description of related prior art [0005] In a typical nuclear water reactor such as a pressurized water reactor (PWR), a heavy water reactor (such as CANDU), or a boiling water reactor (BWR), the reactor core includes a large number of fuel assemblies, each of which consists of multiple elongated fuel elements or fuel ro...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C3/07G21C3/20
CPCG21C3/07G21C3/20G21C21/02Y02E30/30G21C3/10
Inventor E·J·拉霍达
Owner WESTINGHOUSE ELECTRIC CORP
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