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.
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[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
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