Effects of Cr/Zircaloy-4 coating qualities for enhanced accident tolerant fuel cladding. (August 2023)
- Record Type:
- Journal Article
- Title:
- Effects of Cr/Zircaloy-4 coating qualities for enhanced accident tolerant fuel cladding. (August 2023)
- Main Title:
- Effects of Cr/Zircaloy-4 coating qualities for enhanced accident tolerant fuel cladding
- Authors:
- Ridley, Mackenzie
Bell, Samuel
Garrison, Ben
Graening, Tim
Capps, Nathan
Su, Yi-Feng
Mouche, Peter
Johnston, Brandon
Kane, Kenneth - Abstract:
- Highlights: Magnetron sputtered Cr coatings on Zircaloy-4 provide increased resistance to cladding rupture during simulated LOCA. Defects in Cr coatings can inhibit resistance to cladding rupture. Crack-free Cr coatings on Zry-4 show similar rupture temperatures as predicted for uncoated Zry-4 with ∼78% thicker cladding walls. 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 Cr2 O3 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.
- Is Part Of:
- Annals of nuclear energy. Volume 188(2023)
- Journal:
- Annals of nuclear energy
- Issue:
- Volume 188(2023)
- Issue Display:
- Volume 188, Issue 2023 (2023)
- Year:
- 2023
- Volume:
- 188
- Issue:
- 2023
- Issue Sort Value:
- 2023-0188-2023-0000
- Page Start:
- Page End:
- Publication Date:
- 2023-08
- Subjects:
- Accident tolerant fuel -- LOCA -- Chromium coatings -- Zircaloy-4 -- HiPIMS -- Cladding
Nuclear energy -- Periodicals
Nuclear engineering -- Periodicals
621.4805 - Journal URLs:
- http://www.sciencedirect.com/science/journal/03064549 ↗
http://catalog.hathitrust.org/api/volumes/oclc/2243298.html ↗
http://www.elsevier.com/journals ↗ - DOI:
- 10.1016/j.anucene.2023.109799 ↗
- Languages:
- English
- ISSNs:
- 0306-4549
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 1043.150000
British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 26796.xml