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Fonseca, F. de A.S. da; Silva Filho, E.
Associacao Brasileira de Ciencias Mecanicas, Rio de Janeiro, RJ (Brazil)1988
Associacao Brasileira de Ciencias Mecanicas, Rio de Janeiro, RJ (Brazil)1988
AbstractAbstract
[en] The thermal-hydraulic parameter values that restrict the operation of a liquid sodium cooled reactor are not established by the average conditions of the coolant in the reactor core but by the extreme conditions of the hot channel. The present work was developed to analysis of hot channel of a sodium cooled reactor, adapting to this reactor an existent simplified model for hot channel of pressurized water reactor. The model was applied for a standard sodium reactor and the results are considered satisfatory. (author)
[pt]
Os valores dos parametros termohidraulicos que limitam o funcionamento de um reator nuclear refrigerado a sodio nao sao estabelecido pelas condicoes medias do refrigerante no nucleo do reator e sim, pelas condicoes extremas no canal mais quente do nucleo. O presente trabalho visa a analise de canal quente do nucleo de reatores refrigerados a sodio, adaptando-se, para eles, um modelo simplificado ja existente para canal quente de nucleo de reatores a agua leve pressurizada. O modelo foi aplicadO para um reator a sodio tipico, obtendo-se resultado satisfatorios. (autor)Original Title
Simulacao numerica simplificada do canal quente de reatores nucleares refrigerados a sodio
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Source
Dec 1988; 4 p; 2. National Meeting of Thermal Science; Aguas de Lindoia, SP (Brazil); 6-8 Dec 1988
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Miscellaneous
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Conference
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