Abstract
Chromium-coated silicon carbide fiber-reinforced ceramic matrix composites are potentially applicable to accident tolerant fuel cladding in light water reactors. Cr-coated silicon carbide composite, chemical vapor deposited silicon carbide, and pure Cr-metal were oxidized in 100% steam at atmospheric pressure for 4 hours using a thermogravimetric analyzer. Post-oxidation chemical analysis, phase identification and microstructural characterization indicates that the Cr coating layers did not adversely affect silicon carbide substrate under these conditions.
| Original language | English |
|---|---|
| Pages | 659-669 |
| Number of pages | 11 |
| State | Published - 2020 |
| Event | 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States Duration: Sep 22 2019 → Sep 27 2019 |
Conference
| Conference | 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 |
|---|---|
| Country/Territory | United States |
| City | Seattle |
| Period | 09/22/19 → 09/27/19 |
Funding
and a dense, protective SiO2 scale forms. Passive oxidation of SiC has been shown to be well-described by This manuscript has been authored by UT-Battelle, LLC under Contract No. DEAC05-00OR22725 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, worldwide 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). The authors acknowledge Mike Howell for collecting the TGA data and Caen Ang for preparing the Cr-SiC/SiC specimens. This work was supported by the US Department of Energy (DOE), Office of Nuclear Energy, under contact DE-AC05-00OR22725 with UT-Battelle, LLC.