Eventos Anais de eventos
ENCIT 2018
Brazilian Congress of Thermal Sciences and Engineering
Experimental Investigation of Critical Velocity in Fuel Element for the RMB Reactor.
Submission Author:
Alfredo José Alvim de Castro , SP
Co-Authors:
Alfredo José Alvim de Castro, Delvonei Andrade
Presenter: Alfredo José Alvim de Castro
doi://10.26678/ABCM.ENCIT2018.CIT18-0685
Abstract
The fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of aluminum-coated 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 inside the fuel element assembly to form channel gaps between them of only a few millimeters wide through which the coolant flows. 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 work an experimental loop capable of high volume flows and a test section that simulates a plate-like fuel element with three cooling channels was 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 had 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.
Keywords
Critical Velocity, plate-type fuel element, experimental analysis, Material Test Reactor, Iterative coupling procedure
