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Fatigue Behavior of Spent Nuclear Fuel Rods in Simulated Transportation Environment

[+] Author Affiliations
Hong Wang, Jy-an John Wang, Hao Jiang

Oak Ridge National Laboratory, Oak Ridge, TN

Paper No. PVP2017-65842, pp. V06BT06A026; 10 pages
  • ASME 2017 Pressure Vessels and Piping Conference
  • Volume 6B: Materials and Fabrication
  • Waikoloa, Hawaii, USA, July 16–20, 2017
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-5800-4
  • Copyright © 2017 by ASME


Nuclear fuel rod is composed of cladding tube and a specified number of fuel pellets contained. In the United States, spent nuclear fuel (SNF) is expected to be transported to at least one storage facility before permanent disposal. The fatigue behavior of spent nuclear fuel (SNF) rods under reversed cyclic bending must be understood in order to evaluate their vibration integrity in a transportation environment. This is especially important for high-burnup SNFs (>45 GWd/MTU). This report presents the experimental results related to Zircaloy (Zry)-4-based surrogate rods and high-burnup SNFs, based on recent work performed at Oak Ridge National Laboratory (ORNL). The surrogate rod was made of Zry-4 cladding and alumina pellets, and high-burnup fuel rods were discharged from H.B. Robinson pressurized water reactor. The reversed cyclic bending testing was conducted at 5 Hz under loading control. The effect of pre-hydriding and burnup or irradiation on the flexural rigidity and fatigue life of cladding-pellet system were discussed. The fatigue data obtained are extremely useful to the future certification of SNF storage and transportation cask.

Copyright © 2017 by ASME



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