Interface characterization of candidate dual-purpose barrier coatings for SiC/SiC accident tolerant fuel cladding

Joey Kabel, Takaaki Koyanagi, Yutai Katoh, Ryan Schoell, Djamel Kaoumi, Caen Ang, Peter Hosemann

Research output: Contribution to conferencePaperpeer-review

3 Scopus citations

Abstract

SiC/SiC composites have gained significant attention as accident tolerant fuel cladding for their high temperature mechanical properties and superior oxidation kinetics in accident scenarios. However, operational LWR coolant and irradiation conditions cause issues regarding SiC matrix dissolution and fission product retention respectively. A potential solution is the application of a dual-purpose (environmental barrier and hermetic seal) coating. The goal of this research is to aid in the down-selection process in identifying the highest performance coating for LWR conditions. One of the most important selection criteria is the coating-substrate mechanical stability. This research presents an investigation of the relationship between fracture strength and microstructure through small scale mechanical testing and TEM analysis. Micro-cantilevers were fabricated across the SiC/coating interfaces on several candidates including PVD Cr and CrN. Testing was performed at ambient and 320°C. The lower-bound average ambient failure strength for the SiC/Cr and SiC/CrN interfaces were on the order of 3.2 GPa and 3-5 GPa respectively. High temperature tests revealed a dramatic reduction in strength, around 0.4GPa. Neutron irradiated SiC/Cr interfaces (~0.5dpa at 330°C) showed slightly reduced failure strength of 2.9 GPa at ambient temperature. A TEM investigation compared irradiated and pristine SiC/Cr interfaces.

Original languageEnglish
Pages1043-1051
Number of pages9
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

The author would like to thank ORNL and the ORAU/ORISE program for enabling time and access to ORNL facilities. The coating and cantilever fabrication were supported by US DOE Office of Nuclear Energy (NE) for the Advanced Fuels Campaign under contact DE-AC05-00OR22725 with ORNL managed by UT Battelle, LLC. The testing was supported by U.S. DOE, Office of NE, Nuclear Science User Facilities program. This work was performed in part at the Analytical Instrumentation Facility (AIF) at North Carolina State University, which is supported by the State of North Carolina and the National Science Foundation (award number ECCS-1542015). The AIF is a member of the North Carolina Research Triangle Nanotechnology Network (RTNN), a site in the National Nanotechnology Coordinated Infrastructure (NNCI). Funding was provided by DOE-Nuclear Energy University Program DE-NE0008768.

FundersFunder number
DOE-Nuclear Energy UniversityDE-NE0008768
National Science FoundationECCS-1542015
U.S. Department of EnergyDE-AC05-00OR22725
Oak Ridge National Laboratory
North Carolina State University
UT-Battelle

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