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ENCIT 2020
18th Brazilian Congress of Thermal Sciences and Engineering
COMPUTATIONAL ASSESSMENT USING SENSITIVITY ANALYSIS OF MORE TOLERANT FUELS
Submission Author:
Daniel de Souza Gomes , SP , Brazil
Co-Authors:
Daniel de Souza Gomes
Presenter: Daniel de Souza Gomes
doi://10.26678/ABCM.ENCIT2020.CIT20-0482
Abstract
. Nuclear technology is trying to solve a significant challenge in improving security operations, avoid nuclear accidents, at the same time, and optimizing the fuel cycle. In 2020, we have 30 countries and a fleet of 440 nuclear reactors in operation, handing over around 13% of the global electricity demand. In the last fifty years, the light water reactors predominate operating with uranium dioxide as fuel and zirconium alloys as cladding. Research on more tolerant fuels has gone to high priority, after the Fukushima disaster in 2011. The new tolerance concepts move towards replacing the standard fuel system using the state-of-the-art options in the near time. This investigation focused on the response of new materials and your physical properties, which are superior to those of the standard fuel system. In close time advanced alloys based on FeCrAl must substitute for zirconium alloys with enhanced corrosion resistance. On the other hand, more tolerant fuels must have a high uranium density, with a better thermal conductivity than uranium dioxide. This study is used as a fuel licensing code to analyze safety criteria working with stochastic models and empirical rule, and it also incorporates a sensitivity analysis.
Keywords
Uranium silicide, Uranium carbide, FeCrAl alloy, FRAPCON, Sensitivity analysis
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