Neutronic analysis of a fuel element with variations in fuel enrichment and burnable poison

The goal was to evaluate the neutronic behavior during the fuel burnup changing the amount of burnable poison and fuel enrichment. For these analyses, it was 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....

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Principais autores:	R de Faria, Felipe Martins, Carlos Velasquez, Angela Fortini, Claubia Pereira
פורמט:	Artigo
שפה:	Inglês
יצא לאור:	Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2019-07-01
סדרה:	Brazilian Journal of Radiation Sciences
נושאים:	neutronic analysis fuel element burnable poison
גישה מקוונת:	https://bjrs.org.br/revista/index.php/REVISTA/article/view/769
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