Page 68 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
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Thermal-hydraulic challenges in liquid-metal-cooled reactors       43

           Weaver, D., Ziada, S., Au-Yang, M., Chen, S., Paidoussis, M., Pettigrew, M., 2000. Flow-
               induced vibrations in power and process plant components progress and prospects.
               J. Pressure Vessel Technol. 122, 339–348.
           Wu, G., Jin, M., Chen, J., Bai, Y., Wu, Y., 2015. Assessment of RVACS performance for small
               size lead-cooled fast reactor. Ann. Nucl. Energy 77, 310–317.
           Yuan, H., Solberg, J., Merzari, E., Kraus, A., Grindeanu, I., 2017. Flow-induced vibration anal-
               ysis of a helical coil steam generator experiment using large eddy simulation. Nucl. Eng.
               Des. 322, 547–562.


           Further reading

           Koloszar, L., Buckingham, S., Planquart, P., Keijers, S., 2017. MyrrhaFoam: a CFD model for
               the study of the thermal hydraulic behavior of MYRRHA. Nucl. Eng. Des. 312, 256–265.
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