Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation

K. A. Terrani, Y. Yang, Y. J. Kim, R. Rebak, H. M. Meyer, T. J. Gerczak

Research output: Contribution to journalArticlepeer-review

104 Scopus citations

Abstract

Abstract Assessment of the thermodynamics of SiC corrosion under light water reactor coolant environments suggests that silica formation is always expected in the range of applicable pH and potential. Autoclave testing of SiC-based materials in the absence of ionizing radiation was performed. The kinetics data from these tests, when compared with kinetics of silica dissolution in water and post-exposure characterization of SiC samples, suggest that oxidation of SiC to form silica is the rate-limiting step for recession of SiC in high temperature water. Oxygen activity in water was determined to play an important role in SiC recession kinetics. A simplified model of a power loop shows the effect of silica dissolution from the hot region (resembling fuel) and deposition in the cold regions.

Original languageEnglish
Article number49157
Pages (from-to)488-498
Number of pages11
JournalJournal of Nuclear Materials
Volume465
DOIs
StatePublished - Jul 1 2015

Funding

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 ). C.M. Silva, X. Hu, Y. Katoh, B. Pint, J. Busby, and L. Snead at ORNL contributed to the experimental investigations and offered useful discussions. T. Koyanagi and C. Ang at ORNL provided useful comments on the manuscript. The work presented in this paper was supported by the Advanced Fuels Campaign of the Fuel Cycle R&D program in the Office of Nuclear Energy, US Department of Energy .

Keywords

  • LWR corrosion
  • SiC cladding

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