Texto completo de evento
Experimental investigation of critical velocity in fuel element for the RMB reactor
Registration in:
aguardando
Author
CASTRO, ALFREDO J.A. de
ANDRADE, DELVONEI A. de
BRAZILIAN CONGRESS OF THERMAL SCIENCES AND ENGINEERING, 17th
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. Conselho Nacional de Desenvolvimento Cient??fico e Tecnol??gico (CNPq) CNPq: 481193/2012-0