NIKOLAS LYMBERIS SCURO
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Artigo IPEN-doc 27846 A simulation model for capacity planning of nuclear fuel plants for research reactors2021 - NEGRO, M.L.N.; DURAZZO, M.; MESQUITA, M.A.; SCURO, N.L.; CARVALHO, E.F.U.; ANDRADE, D.A.The demand for nuclear fuel for research reactors is increasing worldwide. However, some nuclear fuel factories have low production volumes. Literature regarding how to expand the capacity of those facilities in a safe and reliable way is scarce. Thus, the purpose of this work is to propose and validate a conceptual model for increasing the production capacity of such factories. The facilities addressed here are those that produce plate-type fuel elements loaded with LEU U3Si2-Al, which are typically used in nuclear research reactors. Data from a real nuclear fuel plant was collected and applied to the model, thus setting up a case study. Two different strategies, as well as several production scenarios, were conceived for the use of the model. Each scenario experiments with the different possibilities of enlarging capacity. Discrete events simulation was used in order to cover all production scenarios. The tests indicated significant increases in productive capacity, thus showing that the model fully achieved its proposed objective. One of the main conclusions to be highlighted is the model’s effectiveness, which was demonstrated by using the model in two different strategies and obtaining increases in capacity with both of them.Artigo IPEN-doc 24029 Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly2017 - CASTRO, ALFREDO J.A.; SCURO, NIKOLAS L.; ANDRADE, DELVONEI A.The 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.