Abstract
Cr-coated zirconium alloys represent a modern approach to enhance cladding safety during accident scenarios. Two high-power impulse magnetron sputtered Cr-coated Zry-4 systems were subjected to simulated loss-of-coolant accident conditions to investigate cladding performance. The first Cr-coating (4.8 µm thick) was deposited onto Zry-4 cladding and exhibited through-thickness cracking while the second Cr-coating (6.8 µm thick) was deposited with improved deposition parameters onto polished Zry-4 and exhibited no cracking. During burst testing, the coating with a higher density of defects failed to consistently reduce oxidation and exhibited similar burst behavior as Zry-4. In contrast, the second Cr-coating reduced ZrO2 formation through formation of Cr2O3 and displayed enhanced burst temperatures by ∼80 °C compared to Zry-4. Utilizing an empirical relation for burst behavior of zirconium alloys, the 6.8 µm Cr/Zry-4 system displayed enhanced burst temperatures equivalent to an effective 0.464 mm increase in Zry-4 wall thickness, highlighting the value of continuous Cr coatings for accident scenarios.
Original language | English |
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Article number | 109799 |
Journal | Annals of Nuclear Energy |
Volume | 188 |
DOIs | |
State | Published - Aug 2023 |
Funding
The authors would like to thank A. Willoughby and C. O ’Dell from ORNL. The authors would also like to thank J. Keiser and C. Massey for technical review at ORNL. This work was supported through the Advanced Fuels Campaign by the Office of Nuclear Energy within the United States Department of Energy.
Funders | Funder number |
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Nuclear Energy | |
U.S. Department of Energy | |
Oak Ridge National Laboratory |
Keywords
- Accident tolerant fuel
- Chromium coatings
- Cladding
- HiPIMS
- LOCA
- Zircaloy-4