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Technical Paper

On the Vibrational Behavior of Pressurized Water Reactor Fuel Rods

Pages 483-491 | Published online: 12 May 2017

References

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  • K. L. Schmugar, “Vibrational Characteristics and Wear of Fuel Rods,” Proc. 4th Int. Conf. Structural Mechanics in Reactor Technology, San Francisco, California, August 15–19, 1977, CONF-770815, paper D3/9 (1977).
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  • N. Hoppe et al., “COMETHE III-H for Fuel Rod Behavior Predictions”, ASME Winter Annual Meeting, Houston, Texas, November 30-December 4, 1975.
  • A. Preumont, “Analyse Sismique du Coeur d’un Réacteur Nucléaire PWR”, PhD Thesis, Université de Liège (1981).
  • D. J. Gorman, “An Analytical, and Experimental Investigation of the Vibration of Cylindrical Reactor Fuel Elements in Two-Phase Parallel Flow,” Nucl. Sci. Eng., 44, 277(1971).
  • A. Preumont, P. Thomson, and J. Parent, “Seis mic Analysis of PWR-RCC Fuel Assemblies,” Nucl. Eng. Des., 70 (to be published 1982).

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