Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. (December 2019)
- Record Type:
- Journal Article
- Title:
- Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. (December 2019)
- Main Title:
- Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding
- Authors:
- Dabney, Tyler
Johnson, Greg
Yeom, Hwasung
Maier, Ben
Walters, Jorie
Sridharan, Kumar - Abstract:
- Highlights: Two FeCrAl alloys were deposited onto Zircaloy-4 substrates via cold spray process. Corrosion/oxidation tests for FeCrAl alloys coated samples at 400 °C steam and 1200 °C air. The addition of a cold sprayed Mo-interlayer prevented interdiffusion between Fe and Zr at temperatures above 950 °C. Abstract: Two FeCrAl alloy coatings with different Cr and Al contents were deposited on Zr-alloy substrates via the cold spray deposition method to study the efficacy of these coatings to improve the accident tolerance of Zr-alloy fuel cladding in light water reactors (LWRs). First, the coatings were tested in a 400 °C steam autoclave for 72 h as an accelerated method to simulate the normal LWR operating conditions. In these tests, both coatings resulted in notable improvements in oxidation resistance compared to the Zr-alloy, with the higher Cr containing coating exhibiting a thinner oxide layer. Both coatings provided good oxidation resistance when tested in 1200 °C ambient air environment; however, the formation of a low melting point eutectic (~928 °C) between Fe and Zr resulted in significant melting associated with inter-diffusion between Fe in the coating and the Zr in the substrate. Therefore, to take advantage of the superior oxidation resistance that FeCrAl coatings can provide, a Mo interlayer was deposited, also by the cold spray process, in-between the protective FeCrAl coating and the Zr-alloy substrate, thus creating a dual cold spray layer accident tolerantHighlights: Two FeCrAl alloys were deposited onto Zircaloy-4 substrates via cold spray process. Corrosion/oxidation tests for FeCrAl alloys coated samples at 400 °C steam and 1200 °C air. The addition of a cold sprayed Mo-interlayer prevented interdiffusion between Fe and Zr at temperatures above 950 °C. Abstract: Two FeCrAl alloy coatings with different Cr and Al contents were deposited on Zr-alloy substrates via the cold spray deposition method to study the efficacy of these coatings to improve the accident tolerance of Zr-alloy fuel cladding in light water reactors (LWRs). First, the coatings were tested in a 400 °C steam autoclave for 72 h as an accelerated method to simulate the normal LWR operating conditions. In these tests, both coatings resulted in notable improvements in oxidation resistance compared to the Zr-alloy, with the higher Cr containing coating exhibiting a thinner oxide layer. Both coatings provided good oxidation resistance when tested in 1200 °C ambient air environment; however, the formation of a low melting point eutectic (~928 °C) between Fe and Zr resulted in significant melting associated with inter-diffusion between Fe in the coating and the Zr in the substrate. Therefore, to take advantage of the superior oxidation resistance that FeCrAl coatings can provide, a Mo interlayer was deposited, also by the cold spray process, in-between the protective FeCrAl coating and the Zr-alloy substrate, thus creating a dual cold spray layer accident tolerant coated cladding concept. The wear resistance of the FeCrAl coating was superior to the Zr-alloy substrate based on pin-on-disk wear tests, providing an indication of the benefits of such coatings to reduce grit-to-rod fretting (GTRF) damage. The feedstock powders, microstructure, phases, hardness of coatings, as well as oxide and inter-diffusion layers of oxidized coatings were examined using SEM, XRD, and XPS characterization techniques. … (more)
- Is Part Of:
- Nuclear materials and energy. Volume 21(2019)
- Journal:
- Nuclear materials and energy
- Issue:
- Volume 21(2019)
- Issue Display:
- Volume 21, Issue 2019 (2019)
- Year:
- 2019
- Volume:
- 21
- Issue:
- 2019
- Issue Sort Value:
- 2019-0021-2019-0000
- Page Start:
- Page End:
- Publication Date:
- 2019-12
- Subjects:
- Zircaloy-4 -- FeCrAl coating -- Cold spray process -- High temperature oxidation -- Interdiffusion barrier
Nuclear energy -- Periodicals
Nuclear fuels -- Periodicals
Nuclear reactors -- Materials -- Periodicals
Radioactive substances -- Periodicals
621.4833 - Journal URLs:
- http://www.sciencedirect.com/science/journal/23521791 ↗
http://www.sciencedirect.com/ ↗ - DOI:
- 10.1016/j.nme.2019.100715 ↗
- Languages:
- English
- ISSNs:
- 2352-1791
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 12592.xml