Short communication on "self-crack-healing behavior of oxide formed on a zirconium alloy cladding tube"

被引：5
作者：
Lee, Cheol Min [1 ]
Kim, Gyeonghun [2 ]
Sohn, Dong-Seong [2 ]
Han, Young-Soo [1 ]
Mok, Yong-Kyoon [3 ]
机构：
[1] Korea Atom Energy Res Inst, 989-111 Daedeok Daero, Daejeon 34057, South Korea
[2] Ulsan Natl Inst Sci & Technol, 50 UNIST Gil, Ulsan 689798, South Korea
[3] KEPCO Nucl Fuel, 989 Beon Gil 242, Daejeon 34057, South Korea
来源：
JOURNAL OF NUCLEAR MATERIALS | 2019年 / 526卷
关键词：
Fuel cladding; Zirconium alloy; Oxidation; Corrosion; Scanning electron microscopy (SEM); Crack; Self-crack-healing; ACCIDENT-TOLERANT FUEL; HIGH-TEMPERATURE STEAM; OXIDATION BEHAVIOR; PREFORMED OXIDES; PHASE; ZIRCALOY-4; KINETICS;
D O I：
10.1016/j.jnucmat.2019.151749
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The oxidation of zirconium alloys is largely influenced by cracks in the oxide layers. It was reported that cracks formed in ZrO2/Al2O3 can be healed by the phase transformation of ZrO2. 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 degrees C, but not healed after oxidation at 1000 and 1100 degrees C. It appears that this crack healing behavior is related to the phase transformation of ZrO2. (C) 2019 Elsevier B.V. All rights reserved.
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页数：5
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