Volume 9: Student Paper Competition 2018
DOI: 10.1115/icone26-81464
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Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding

Abstract: Nuclear fuel cladding is an integral part of nuclear reactors and choosing the proper material is imperative to the design of a reactor. In this paper, the neutronic properties and the fuel performance of a 17 × 17 Westinghouse Pressurized Water Reactor (PWR) assembly using ceramic matrix composites (CMC) Silicone Carbide (SiC) as a cladding material is investigated. The material analysis is compared against traditional Zircaloy-4 cladding used in a 17 × 17 Westinghouse PWR assembly. The codes used in the anal… Show more

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