Numerical methodology for fluid-structure interaction analysis of nuclear fuel plates under axial flow conditions
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2018
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Nuclear Engineering and Design
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Shell-type fuel elements are widely used in nuclear research reactors. The nuclear fuel is contained in parallel shells, flat or curved, that are separated by narrow channels through which the fluid flows to remove the heat generated by fission reactions. A major problem of this fuel assembly design is the hydraulic instability of the shells caused by the high flow velocities. The objective of the study presented here is the development of a fluid-structure interaction methodology to investigate numerically the onset of hydroelastic instability of flat-shell-type fuel elements, also known as plate-type fuel assemblies, under axial flow conditions. The system analyzed consists of two nuclear fuel plates bounded by three-equal coolant channels. It is developed using the commercial codes ANSYS CFX for modeling the fluid flow and ANSYS Mechanical to model the plates. The fluid-structure interaction methodology predicts a behavior consistent with other theoretical and experimental works. Particularly, the maximum deflection of the plates is detected at the leading edge and it is a linear function of the square of the fluid velocity up to the Miller’s theoretical value. For velocities above this value, a nonlinear relationship is observed. This relationship indicates that structural changes are taking place in the plates. Furthermore, for fluid velocities greater than the Miller’s velocity, an extra deflection peak is observed near the trailing edge of the plates. Thus, structural alterations also happen along the length of the flat-shells.
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MANTECON, JAVIER G.; MATTAR NETO, MIGUEL. Numerical methodology for fluid-structure interaction analysis of nuclear fuel plates under axial flow conditions. Nuclear Engineering and Design, v. 333, p. 76-86, 2018. DOI: 10.1016/j.nucengdes.2018.04.009. Disponível em: http://repositorio.ipen.br/handle/123456789/28966. Acesso em: 01 Jul 2024.
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