Mechanical Behavior of FeCrAl and Other Alloys Following Exposure to LOCA Conditions Plus Quenching

  • Evan J. Dolley
  • Michael Schuster
  • Cole Crawford
  • Raul B. RebakEmail author
Conference paper
Part of the The Minerals, Metals & Materials Series book series (MMMS)


The US Department of Energy is working with commercial fuel vendors to develop advanced technology or accident tolerant fuels (ATF) for the current fleet of light water power reactors. General Electric and Oak Ridge National Laboratory are evaluating the concept of using iron-chrome-aluminum (FeCrAl) alloys as cladding for the current fuel of uranium dioxide pellets. In the case of a loss of coolant accident, the reactor may need to be flooded with fresh water when the cladding could be in the temperature range above 1000 ℃. It is important to determine the integrity of the cladding material after being quenched in water. Tests were performed for six alloys of interest which were exposed for 2 h at 1200 ℃ in air, argon or steam and then quenched in ambient temperature water. The resulting mechanical properties were evaluated and compared with the mechanical properties of the as received material. The FeCrAl alloy retains its yield strength after the high temperature excursions, with minimal oxidation but with some loss of ductility.


FeCrAl cladding Accident tolerant Thermal shock Mechanical properties 



The authors would like to thank the characterization lab at GE Global Research, including Mike Larsen, Jae-Hyuk Her and Ian Spinelli. Great thanks to Lisa Sciubba at Lucideon (Schenectady, NY) for metallographic cross sections. The funding support from GE Hitachi is gratefully acknowledged. This material is based upon work supported by the Dept. of Energy [National Nuclear Security Administration] under Award Number DE-NE0008221. This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.


  1. 1.
    J. Kotek, Fukushima: Looking Back, Looking Ahead. (Retrieved 2016 04 19)Google Scholar
  2. 2.
    US Department of Energy, Development of Light Water Reactor Fuels with Enhanced Accident Tolerance, Report to Congress, June 2015Google Scholar
  3. 3.
    S. Bragg-Sitton et al. (10 more names), Advanced Fuels Campaign LWR Accident Tolerant Fuel Performance Metrics, Idaho National Laboratory, Advanced Fuels Campaign, FCRD-FUEL-2013-000264, INL/EXT-13-30226 (February 2014)Google Scholar
  4. 4.
    J. Carmack, F. Goldner, Forward for special JNM issue on accident tolerant fuels for LWRs. J. Nuclear Mater. 448 (1–32014), 373 (2014)CrossRefGoogle Scholar
  5. 5.
    V.K. Dhir, R.B. Duffey, I. Cation, Quenching Studies on a Zircaloy Rod Bundle. J. Heat Transfer 103(1981), 293–299 (1981)CrossRefGoogle Scholar
  6. 6.
    F.S. Gunnerson, T.R. Yackle, Quenching and rewetting of nuclear fuel rods. Nucl. Technol. 54(1), 113–117 (1981)CrossRefGoogle Scholar
  7. 7.
    R.B. Rebak, Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurg. Mater. Trans. E 2E, 197–207 (2015)Google Scholar
  8. 8.
    K.A. Terrani, S.J. Zinkle, L.L. Snead, Advanced oxidation-resistant iron-based alloys for LWR fuel cladding. J. Nucl. Mater. 448(1–3), 420–435 (2014)CrossRefGoogle Scholar
  9. 9.
    R.E. Stachowski1, R.B. Rebak, W.P. Gassmann, J. Williams, Progress of GE Development of Accident Tolerant Fuel FeCrAl Cladding. Top Fuel 2016, Boise Idaho, September 2016Google Scholar
  10. 10.
    B.A. Pint, K.A. Terrani, Y. Yamamoto, L.L. Snead, Material selection for accident tolerant fuel cladding. Met. Mater. Trans. E 2E, 190 (2015)Google Scholar
  11. 11.
    K.A. Terrani, B.A. Pint, Y.-J. Kim, K.A. Unocic, Y. Yang, C.M. Silva, H.M. Meyer III, R.B. Rebak, Uniform corrosion of FeCrAl alloys in LWR coolant environments. J. Nucl. Mater. 479, 36–47 (2016)CrossRefGoogle Scholar

Copyright information

© The Minerals, Metals & Materials Society 2019

Authors and Affiliations

  • Evan J. Dolley
    • 1
  • Michael Schuster
    • 1
  • Cole Crawford
    • 1
  • Raul B. Rebak
    • 1
    Email author
  1. 1.GE Global ResearchSchenectadyUSA

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