Neutronic analysis of a fuel element with variations in fuel enrichment and burnable poison
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Universidade Federal de Minas Gerais
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In this work, the goal was to evaluate the neutronic behavior during the fuel burnup changing the amount of
burnable poison and fuel enrichment. The analyses used a 17 x 17 PWR fuel element, simulated using the 238
groups library cross-section collapsed from ENDF/BVII.0 and TRITON module of SCALE 6.0 code system. The
results confirmed the effective action of the burnable poison in the criticality control, especially at Beginning Of
Cycle (BOC) and in the burnup kinetics, because at the end of the fuel cycle there was a minimal residual
amount of neutron absorbers (155Gd and 157Gd), as expected, showing the burnup of the Gd in the simulation
methodology adopted. Furthermore, the results show that increasing the Gd insertion percentage does not
change its final residual amount. At the end of the cycle, the fuel element was still critical for all the simulated
situations, which indicates the possibility of extending the fuel burnup.
Abstract
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Análise por ativação nuclear, Combustiveis
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Neutronic analysis, Fuel element, Burnable poison
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https://www.bjrs.org.br/revista/index.php/REVISTA/article/view/769