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Short communication on "self-crack-healing behavior of oxide formed on a zirconium alloy cladding tube".
- Source :
-
Journal of Nuclear Materials . Dec2019, Vol. 526, pN.PAG-N.PAG. 1p. - Publication Year :
- 2019
-
Abstract
- The oxidation of zirconium alloys is largely influenced by cracks in the oxide layers. It was reported that cracks formed in ZrO 2 /Al 2 O 3 can be healed by the phase transformation of ZrO 2. Here, we conducted several experiments to determine whether this also holds true for zirconium alloys. The experimental results showed that the cracks at the oxide-metal interface were healed after oxidation at 1200 °C, but not healed after oxidation at 1000 and 1100 °C. It appears that this crack healing behavior is related to the phase transformation of ZrO 2. Image 1 • Self-crack-healing behavior was observed from the oxide formed on a zirconium alloys cladding tube. • Self-crack-healing behavior occurred at temperatures above 1200 °C, but not below 1100 °C. • This phenomenon appears to be related to the phase transformation of ZrO 2. [ABSTRACT FROM AUTHOR]
- Subjects :
- *ZIRCONIUM alloys
*ZIRCALOY-2
*ZIRCONIUM oxide
*TUBES
Subjects
Details
- Language :
- English
- ISSN :
- 00223115
- Volume :
- 526
- Database :
- Academic Search Index
- Journal :
- Journal of Nuclear Materials
- Publication Type :
- Academic Journal
- Accession number :
- 141785500
- Full Text :
- https://doi.org/10.1016/j.jnucmat.2019.151749