Transient cfd analysis of the flow inversion of the nuclear research reactor IEA-R1
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2018
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EUROPEAN RESEARCH REACTOR CONFERENCE
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The IEA-R1 research reactor works with a downflow direction, but after pumps shutdown during a LOFA test, the reactor shutdown. The heat decay will be removed by natural convection, which is an upward flow, originating flow inversion. Using the Instrumented Fuel Element designed at the Institute for Energy and Nuclear Research (IPEN), the loss of flow accident (LOFA) was analyzed along instrumented fuel plates. The preliminary results showed temperature peaks during inversion, which is as much representative as in nominal operation at 3.5MW. Therefore, these experimental data lead a construction and validation of a transient three-dimensional numerical analysis for a single fuel channel using the ANSYS-CFX® commercial code. The numerical results show improvement in obtaining more properties, e.g., wall heat transfer coefficient, which is usually obtained through empirical correlations.
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SCURO, N.L.; SANTOS, P.G.; UMBEHAUN, P.E.; ANDRADE, D.A.; ANGELO, E.; ANGELO, G. Transient cfd analysis of the flow inversion of the nuclear research reactor IEA-R1. In: EUROPEAN RESEARCH REACTOR CONFERENCE, March 11-15, 2018, Munich, Germany. Proceedings... Brussels, Belgium: European Nuclear Society, 2018. Disponível em: http://repositorio.ipen.br/handle/123456789/29003. Acesso em: 18 Feb 2025.
Esta referência é gerada automaticamente de acordo com as normas do estilo IPEN/SP (ABNT NBR 6023) e recomenda-se uma verificação final e ajustes caso necessário.