Abstract
Iron-chromium-aluminum (FeCrAl) coatings deposited on Zircaloy 2 (Zy2) and yttria-stabilized zirconia (YSZ) by magnetron sputtering have been tested with respect to oxidation weight gain in high-temperature steam. In addition, autoclave testing of FeCrAl-coated Zy2 coupons under pressure-temperature-dissolved oxygen coolant conditions representative of a boiling water reactor (BWR) environment has been performed. Four different FeCrAl compositions have been tested in 700 °C steam; compositions that promote alumina formation inhibited oxidation of the underlying Zy2. Parabolic growth kinetics of alumina on FeCrAl-coated Zy2 is quantified via elemental depth profiling. Autoclave testing under normal BWR operating conditions (288 °C, 9.5 MPa with normal water chemistry) up to 20 days demonstrates observable weight gain over uncoated Zy2 simultaneously exposed to the same environment. However, no FeCrAl film degradation was observed. The 900 °C eutectic in binary Fe-Zr is addressed with the FeCrAl-YSZ system.
Original language | English |
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Pages (from-to) | 327-338 |
Number of pages | 12 |
Journal | Journal of Nuclear Materials |
Volume | 470 |
DOIs | |
State | Published - Mar 1 2016 |
Externally published | Yes |
Funding
This work was performed with support from the US Department of Energy Nuclear Energy University Programs Integrated Research Project under contract number IRP-12-4728 . In addition, this work was carried out in part in the Frederick Seitz Materials Research Laboratory Central Facilities, University of Illinois, which are partially supported by the US Department of Energy under Grants DE-FG02-07ER46453 and DE-FG02-07ER46471 . We are grateful to Y. Miao (UIUC) for help with SEM, STEM, and EDS sample preparation and analysis. In addition, assistance of R. Haasch (UIUC), J. Mabon (UIUC), H. Zhou (UIUC), and M. Sardela (UIUC) with AES, SEM, STEM, and XRD analysis, respectively, is gratefully acknowledged.
Keywords
- Alumina
- Corrosion
- FeCrAl
- LWR cladding
- Oxidation
- Protective coatings