Please use this identifier to cite or link to this item: http://hdl.handle.net/1843/45015
Type: Artigo de Periódico
Title: Sensitivity analysis of a PWR fuel element using zircaloy and silicon carbide claddings
Authors: Rochkhudson Batista de Faria
Patrícia Amélia de Lima Reis
Carlos Eduardo Velasquez Cabrera
Javier González Mantecón
Adolfo Romero Hamers
Antonella Lombardi Costa
Claubia Pereira Bezerra Lima
Abstract: In 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.
Subject: Engenharia nuclear
language: eng
metadata.dc.publisher.country: Brasil
Publisher: Universidade Federal de Minas Gerais
Publisher Initials: UFMG
metadata.dc.publisher.department: ENG - DEPARTAMENTO DE ENGENHARIA NUCLEAR
Rights: Acesso Restrito
metadata.dc.identifier.doi: http://dx.doi.org/10.1016/j.nucengdes.2017.05.006
URI: http://hdl.handle.net/1843/45015
Issue Date: 2017
metadata.dc.url.externa: https://www.sciencedirect.com/science/article/pii/S0029549317302261
metadata.dc.relation.ispartof: Nuclear Engineering and Design
Appears in Collections:Artigo de Periódico

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