Advertisement

Hydrothermal Corrosion of SiC Materials for Accident Tolerant Fuel Cladding with and Without Mitigation Coatings

  • Stephen S. RaimanEmail author
  • Caen Ang
  • Peter Doyle
  • Kurt A. Terrani
Conference paper
Part of the The Minerals, Metals & Materials Series book series (MMMS)

Abstract

As a candidate material for accident-tolerant fuel cladding for light water reactors (LWR), SiCf–SiC composite materials possess many attractive properties. However, prior work has shown that SiC is susceptible to aqueous dissolution in LWR coolant environments. To address this issue, candidate coatings have been developed to inhibit dissolution. For this study, CVD SiC samples were prepared with Cr, CrN, TiN, ZrN, NiCr, and Ni coatings. Uncoated SiC and SiCf–SiC samples were also prepared. The samples were exposed for 400 h in 288 ℃ water with 2 wppm DO in a constantly-refreshing autoclave to simulate BWR–NWC. Cr and Ni coated samples lost less mass than the uncoated SiC sample, indicating an improvement in performance. The CrN coating resisted oxidation, but some of the coating was lost due to poor adhesion. The TiN coated sample gained significant mass due to oxidation of the coating. ZrN and NiCr coatings showed significant corrosion attack. SiCf–SiC ceramic matrix composite materials dissolved much faster than the CVD SiC sample, demonstrating the need for mitigation coatings if CMCs are to be used in LWRs. This work demonstrates the promise of Cr, Ni and CrN coatings for corrosion mitigation in LWRs, and shows that NiCr and ZrN are not promising coating materials.

Keywords

Silicon carbide Accident-tolerant fuel Coatings Corrosion BWR–NWC 

Notes

Acknowledgements

The authors acknowledge the valuable assistance of Adam Willoughby and Tracie Lowe. This research was funded by U.S. Department of Energy’s Office of Nuclear Energy, Advanced Fuel Campaign.

This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).

References

  1. 1.
    D.M. Carpenter, An Assessment of Silicon Carbide as a Cladding Material for Light Water Reactors, PhD Thesis, MIT (2010)Google Scholar
  2. 2.
    S.J. Zinkle, K.A. Terrani, J.C. Gehin, L.J. Ott, L.L. Snead, Accident tolerant fuels for LWRs: a perspective. J. Nucl. Mater. 448(1), 374–379 (2014)CrossRefGoogle Scholar
  3. 3.
    K.A. Terrani, B.A. Pint, C.M. Parish, C.M. Silva, L.L. Snead, Y. Katoh, Silicon Carbide Oxidation in steam up to 2 MPa. J. Am. Ceram. Soc. 97(8), 2331–2352 (2014)CrossRefGoogle Scholar
  4. 4.
    T. Cheng, J.R. Keiser, M.P. Brady, K.A. Terrani, B.A. Pint, Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure. J. Nucl. Mater. 427, 396–400 (2012)CrossRefGoogle Scholar
  5. 5.
    L.J. Ott, K.R. Robb, D. Wang, Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. J. Nucl. Mater. 448(1), 520–533 (2014)CrossRefGoogle Scholar
  6. 6.
    K.A. Terrani, Y. Yang, Y.-J. Kim, R. Rebak, H.M. Meyer, T.J. Gerczak, Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. J. Nucl. Mater. 465, 488–498 (2015)CrossRefGoogle Scholar
  7. 7.
    I. Younker, M. Fratoni, Neutronic evaluation of coating and cladding materials for accident tolerant fuels. Prog. Nucl. Energy 88, 10–18 (2016)CrossRefGoogle Scholar
  8. 8.
    J.-H. Park, H.-G. Kim, J. Park, Y.-I. Jung, D.-J. Park, Y.-H. Koo, High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings. Surf. Coatings Technol. 280, 256–259 (2015)CrossRefGoogle Scholar
  9. 9.
    E. Alat, A.T. Motta, R.J. Comstock, J.M. Partezana, D.E. Wolfe, Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding. J. Nucl. Mater. 478, 236–244 (2016)CrossRefGoogle Scholar

Copyright information

© The Minerals, Metals & Materials Society 2019

Authors and Affiliations

  • Stephen S. Raiman
    • 1
    Email author
  • Caen Ang
    • 1
  • Peter Doyle
    • 1
  • Kurt A. Terrani
    • 1
  1. 1.Oak Ridge National LaboratoryOak RidgeUSA

Personalised recommendations