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|metadata.dc.title.evento:||World TRIGA users conference, 3|
|Affiliation:||Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil|
Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil
|Keywords:||TRIGA- Brazil reactor;critical heat flux|
|Abstract:||Experimental and analytical studies have been performed in the IPR-R1 TRIGA Mark-1 reactor at Nuclear Technology Development Center (CDTN), Brazil, to find out the temperature distribution under steady-state conditions as a function of the reactor power. The flow distribution in the cooling channels and the heat-transfer coefficient on the heated surface were obtained experimentally. These results permitted to make the prediction of critical heat flux (CHF), which defines the limit of fuel heat removal.|
|Appears in Collections:||Trabalho apresentado em evento|
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