Experimental investigation of critical velocity in fuel element for the RMB reactor

Carregando...
Imagem de Miniatura

Data

Data de publicação

2018

Orientador

Título da Revista

ISSN da Revista

Título do Volume

É parte de

É parte de

É parte de

É parte de

BRAZILIAN CONGRESS OF THERMAL SCIENCES AND ENGINEERING, 17th
Exportar
Mendeley

Projetos de Pesquisa

Unidades Organizacionais

Fascículo

Resumo
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.

Como referenciar
CASTRO, ALFREDO J.A. de; ANDRADE, DELVONEI A. de. Experimental investigation of critical velocity in fuel element for the RMB reactor. In: BRAZILIAN CONGRESS OF THERMAL SCIENCES AND ENGINEERING, 17th, November 25-28, 2018, Águas de Lindóia, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Engenharia e Ciências Mecânicas, 2018. Disponível em: http://repositorio.ipen.br/handle/123456789/29743. Acesso em: 30 Dec 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.

Agência de fomento

Coleções