CASTRO, ALFREDO J.A.SCURO, NIKOLAS L.ANDRADE, DELVONEI A.2018-01-032018-01-03CASTRO, ALFREDO J.A.; SCURO, NIKOLAS L.; ANDRADE, DELVONEI A. Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. <b>Proceedings...</b> Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28204.http://repositorio.ipen.br/handle/123456789/28204The fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of aluminumcoated fuel plates containing the core of uranium silica (U3Si2) dispersed in an aluminum matrix. These plates have a thickness of the order of millimeters and are much longer in relation to their thickness. They are arranged in parallel in the assembly of the fuel element to form channels between them a few millimeters in thickness, through which there is a flow of the coolant. This configuration, combined with the need for a flow at high flow rates to ensure the cooling of the fuel element in operation, may create problems of mechanical failure of fuel plate due to the vibration induced by the flow in the channels. In the case of critical velocity excessive permanent deflections of the plates can cause blockage of the flow channel in the reactor core and lead to overheating in the plates. For this study an experimental bench capable of high volume flows and a test section that simulates a plate-like fuel element with three cooling channels were developed. The dimensions of the test section were based on the dimensions of the Fuel Element of the Brazilian Multipurpose Reactor (RMB), whose project is being coordinated by the National Commission of Nuclear Energy (CNEN). The experiments performed attained the objective of reaching Miller's critical velocity condition. The critical velocity was reached with 14.5 m/s leading to the consequent plastic deformation of the flow channel plates.openAccesscritical velocitydeformationexperimental datafluid flowfuel assembliesfuel platesmtr reactornuclear fuelsreactor coresTexto completo de eventohttps://orcid.org/0000-0002-6689-3011