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Stress Rupture Characteristics of Zirconium Alloy Cladding Under Closed-End Internal Pressurization

[+] Author Affiliations
B. Marple, Y. J. Song, S. Gollapudi, K. L. Murty

North Carolina State University, Raleigh, NC

I. Charit

University of Idaho, Moscow, ID

Paper No. ICONE16-48006, pp. 385-388; 4 pages
  • 16th International Conference on Nuclear Engineering
  • Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues
  • Orlando, Florida, USA, May 11–15, 2008
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4814-0 | eISBN: 0-7918-3820-X
  • Copyright © 2008 by ASME


An understanding of stress rupture behavior of zirconium alloy cladding tubes is of paramount importance for applications in nuclear reactors. Stress rupture properties of recrystallized Zircaloy-4 alloy were evaluated using burst testing of closed-end thin-walled tubing at varied test temperatures and internal pressures. The rupture data are correlated using the Larson-Miller parameter. The uniform circumferential elongations were also measured from which the hoop creep rates were calculated. These results were fitted to Monkman-Grant relationship with the aim of extrapolating the data to in-service stress levels. Furthermore, the creep data were plotted according to the Dorn equation where a transition in deformation mechanism from ‘power-law’ to ‘power law breakdown’ for Zircaloy-4 was noted. TEM studies corroborated the transition in mechanism from the power-law regime to a power-law breakdown regime.

Copyright © 2008 by ASME



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