Evaluation of the corrosion kinetics of SiC with and without mitigation coatings in LWR chemistries*

Peter Doyle, Stephen Raiman, Caen Ang, Yutai Katoh, Steven Zinkle

Research output: Contribution to conferencePaperpeer-review

4 Scopus citations

Abstract

Since the Fukushima-Daiichi accident in 2011, accident-tolerant fuel (ATF) cladding concepts such as FeCrAl alloys and ceramic matrix composites (CMCs) of SiC have been extensively researched. SiC is desirable for excellent radiation tolerance, mechanical properties, and resistance to oxidation under accident scenarios. However, under standard operating conditions, it may corrode too quickly for use in LWRs. To mitigate these issues, coatings of Cr, CrN, Cr/CrN, and TiN were applied via physical vapor deposition (PVD) on SiC prepared by chemical vapor deposition (CVD). These were exposed, along with uncoated CVD SiC, to temperatures between 288 and 350°C, with 0.15-3 wppm dissolved H2 or 1-4 wppm O2. TiN and CrN coatings did not observe a permanently-protective oxide, potentially due to coating impurities. TiN was found to never be viable, slowly degrading in hydrogenated water, and spalling after ~0.5 µm of oxide growth. In HWC and PWR conditions, CrN did not perceptibly corrode but otherwise degraded, while the multilayer Cr/CrN immediately failed. Cr was a successful mitigation coating in the absence of oxygen. The corrosion kinetics of the SiC substrate was dependent on the surface preparation, with polished SiC leading to predictable linear kinetics, with one rate-limiting step for reactions with oxygen and water.

Original languageEnglish
Pages417-427
Number of pages11
StatePublished - 2019
Event19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019 - Boston, United States
Duration: Aug 18 2019Aug 22 2019

Conference

Conference19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019
Country/TerritoryUnited States
CityBoston
Period08/18/1908/22/19

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 nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow other 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). Adam Willoughby and Tyson Jordan provided valuable assistance on this project. Thanks also to Bruce Pint, Kurt Terrani, and Takaaki Koyanagi for helpful review of this document. The work presented in this paper was supported by the Advanced Fuels Campaign of the Nuclear Technology R&D program in the Office of Nuclear Energy, US Department of Energy.

FundersFunder number
U.S. Department of Energy
Office of Nuclear Energy

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