GOMES, DANIEL de S.GIOVEDI, CLAUDIA2022-03-302022-03-30GOMES, DANIEL de S.; GIOVEDI, CLAUDIA. Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors. In: INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 26th, November 22-26, 2021, Online. <b>Proceedings...</b> Rio de Janeiro, RJ: Associação Brasileira de Engenharia e Ciências Mecânicas - ABCM, 2021. Disponível em: http://repositorio.ipen.br/handle/123456789/32912.http://repositorio.ipen.br/handle/123456789/32912The fuel performance code, Fuel Analysis under Steady-state and Transients (FAST), permits cladding options, such as zirconium alloys and iron-chromium-aluminum (FeCrAl). FAST code support as cladding Kanthal, CM35, and CM36 alloys. We implemented a comparative analysis between ferritic alloys, steel, and zircaloy. Many features of ferritic alloys classify as more tolerant materials, such as high resistance to steam oxidation, reduced hydrogen release, and longer coping time. But the neutron penalty must reduce cladding thickness to let a greater fuel volume. Both ferritic alloys and austenitic steel show higher corrosion resistance, also avoiding hydrogen releases. FeCrAl provides more resistant corrosion cracking than stainless steel. The properties of steel 348 are comparable to those of FeCrAl alloys. Steel exhibits superior thermal conductivity, linear thermal expansion, and mechanical strength. Both offer similar specific heat, melting points, and densities. The chemical composition of the steel has 66% iron and 19% chromium, compared with Kanthal APMT™, which uses 68.8% iron and 22% chromium. The results found real advantages related to safety risks using ferritic cladding materials.openAccessfuelsstainless steelskanthalcladdingaccident-tolerant nuclear fuelszircaloyTexto completo de eventohttps://orcid.org/0000-0002-2181-8704