Sensitivity analysis of a PWR fuel element using zircaloy and silicon carbide claddings

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dc.creatorRochkhudson Batista de Faria
dc.creatorPatrícia Amélia de Lima Reis
dc.creatorCarlos Eduardo Velasquez Cabrera
dc.creatorJavier González Mantecón
dc.creatorAdolfo Romero Hamers
dc.creatorAntonella Lombardi Costa
dc.creatorClaubia Pereira Bezerra Lima
dc.date.accessioned2022-09-08T20:23:33Z
dc.date.accessioned2025-09-09T00:17:59Z
dc.date.available2022-09-08T20:23:33Z
dc.date.issued2017
dc.identifier.doihttp://dx.doi.org/10.1016/j.nucengdes.2017.05.006
dc.identifier.issn1872-759X
dc.identifier.urihttps://hdl.handle.net/1843/45015
dc.languageeng
dc.publisherUniversidade Federal de Minas Gerais
dc.relation.ispartofNuclear Engineering and Design
dc.rightsAcesso Restrito
dc.subjectEngenharia nuclear
dc.subject.otherPWR
dc.subject.otherZircaloy
dc.subject.otherHi-Nicalon type S
dc.titleSensitivity analysis of a PWR fuel element using zircaloy and silicon carbide claddings
dc.typeArtigo de periódico
local.citation.epage111
local.citation.spage103
local.citation.volume320
local.description.resumoIn this paper, the SiC reinforced with Hi-Nicalon type S fibers (SiC HNS) was used as fuel cladding, and its behavior from the neutronic viewpoint was compared with the Zircaloy. To evaluate the average temperature of the fuel, cladding, and moderator used in the neutronic studies, a simplified thermal-hydraulic simulation of the core was performed using the RELAP5 code for the two cladding materials. Then, after that, a standard PWR fuel element was simulated, considering normal conditions of operation at Beginning Of Life (BOL) and full power, and using the average temperatures coming from the RELAP5 code calculation. The effects of burnable poison rods and temperature feedback on the core neutron multiplication factor have been evaluated changing the clad material at criticality steady state condition. Finally, the fuel element is analyzed during burnup. The neutronic analysis was made using the SCALE 6.0 (Standardized Computer Analysis for Licensing Evaluation) code.
local.publisher.countryBrasil
local.publisher.departmentENG - DEPARTAMENTO DE ENGENHARIA NUCLEAR
local.publisher.initialsUFMG
local.url.externahttps://www.sciencedirect.com/science/article/pii/S0029549317302261

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