Hydrogen-damage interactions in yttria-stabilized zirconia

被引：3
|
作者：
Shutthanandan, V [1 ]
Thevuthasan, S [1 ]
Young, JS [1 ]
Orlando, TM [1 ]
Weber, WJ [1 ]
机构：
[1] Pacific NW Natl Lab, Environm Mol Sci Lab, Richland, WA 99352 USA
来源：
JOURNAL OF NUCLEAR MATERIALS | 2001年 / 289卷 / 1-2期
关键词：
Number:; -; Acronym:; DMSE; Sponsor: Division of Materials Sciences and Engineering; PNNL; Sponsor: Pacific Northwest National Laboratory; Sponsor:; Battelle;
D O I：
10.1016/S0022-3115(00)00692-9
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Hydrogen diffusion and accumulation in oxidized Zr(ZrO(2)) and oxide-metal interfaces lead to hydrogen induced cracking in Zr-based compounds that are extensively used in nuclear reactors. In this study, the interaction of hydrogen with irradiation damage in (001) single crystals of yttria-stabilized zirconia (Y-ZrO(2)) has been investigated as a function of damage accumulation and temperature. Samples were irradiated with 40 keV hydrogen ions at a temperature of 120 K to ion fluences of 5 x 10(16) and 1 x 10(17) ions/cm(2), and isochronal experiments were performed in the temperature range from 300 to 770 K in 100 K steps. Damage accumulation and hydrogen profile measurements indicate unusual damage recovery behavior, pinning of hydrogen by damage, and surface deformation due to hydrogen blisters and bubbles. (C) 2001 Published by Elsevier Science B.V.
引用
收藏
页码：128 / 135
页数：8
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