Use este identificador para citar ou linkar para este item: http://carpedien.ien.gov.br:8080/handle/ien/2463
Tipo: conferenceObject
Título: Artificial neural network used in the study of sensitives in iris reactor pressurizer
Autor(es): Costa, Samuel Pimentel
Lima, Fernando Roberto de Andrade
Lapa, Celso Marcelo Franklin
Lira, Carlos Alberto Brayner de Oliveira
Resumo: In general, the technique of sensibility analysis studies the behavior of the ratio between the variation of output results and the variation of input parameters. This study performed in the reactor pressurizer, which is a component responsible for control of the pressure inside the vessel, has fundamental importance in designing the security of any concept of advanced reactor. Above all, for its feature of passive action of the pressurizer (there is no spray), this analysis becomes a necessary step for safety and performance of the plant. The direct method through code MODPRESS, which represents the pressurizer model of the International Reactor Innovative and Secure (IRIS), has required large computational effort. Unlike this method, Artificial Neural Networks (ANN), beyond faster, do not require a typical linear behavior of the system. Moreover, they can also use experimental data for their training and learning. If the ANN are satisfactory in this theoretical case may be used for future mapping and forecasting of the behavior of various phenomena in both plant operation and small-scale experiment to be installed in CRCN-NE. Based on the results obtained in this study, one can conclude that the artificial neural networks are presented as an alternative to MODPRESS code, as well as a great tool to calculate the sensitivity coefficient.
Palavras-chave: INAC 2011
Artificial Neural Network
Nuclear reactor
MODPRESS
Idioma: eng
País: Brasil
Editor: Instituto de Engenharia Nuclear
Sigla da Instituição: IEN
Tipo de Acesso: openAccess
URI: http://carpedien.ien.gov.br:8080/handle/ien/2463
Data do documento: Out-2011
Aparece nas coleções:Engenharia e Segurança de Reatores Nucleares - Trabalhos de Congresso

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