Nanoindentation studies of high-temperature oxidized Zircaloy-4 with and without hydrogen

被引:10
|
作者
Ito, Masato [1 ]
Muta, Hiroaki [1 ]
Setoyama, Daigo [1 ]
Uno, Masayoshi [1 ]
Yamanaka, Shinsuke [1 ]
机构
[1] Osaka Univ, Grad Sch Engn, Div Sustainable Energy & Environm Engn, Osaka 5650871, Japan
关键词
nuclear reactor materials; mechanical property; microstructure; oxidation; atomic force microscopy (AFM);
D O I
10.1016/j.jallcom.2007.02.070
中图分类号
O64 [物理化学(理论化学)、化学物理学];
学科分类号
070304 ; 081704 ;
摘要
The nanoindentation tests on high-temperature oxidized fuel claddings with/without hydrogenation were performed in order to verify the influence of hydrogen on mechanical behavior of the cladding under a loss of coolant accident (LOCA) condition. Hydrogenated and non-hydrogenated Zircaloy-4 cladding tubes were oxidized in steam at the temperature of 1373-1393 K followed by quenching. The nanoindentation test was performed in the area of inhomogeneous structure called as the Widmann-Statten structure, composed of the needle-like a-zirconium grains (alpha' phase) and the matrix (alpha phase). The mechanical properties viz. hardness and elastic modulus were evaluated for a' phase and matrix alpha phase, separately. The hardness and elastic modulus of alpha' phase are much higher than those of the matrix alpha phase due to its higher oxygen concentration. There was no significant difference of mechanical properties between the samples with and without hydrogen. (C) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:639 / 642
页数:4
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