Evaluation of mechanical properties of irradiated zirconium alloys in the vicinity of the metal-oxide interface

被引:9
作者
Colldeweih, Aaron W. [1 ]
Baris, Adrienn [1 ]
Spatig, Philippe [1 ]
Abolhassani, Sousan [1 ]
机构
[1] Paul Schemer Inst, Lab Nucl Mat Nucl Energy & Safety, CH-5232 Villigen, Switzerland
来源
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING | 2019年 / 742卷
关键词
Zirconium oxide; Oxygen rich metal at the metal-oxide interface; Oxidation and hydrogen uptake; Irradiation; Focused ion beam; Micro-pillar nano-indentation; FUEL; CERAMICS; TUBES;
D O I
10.1016/j.msea.2018.09.107
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
The mechanical properties of oxides play an important role on the protection of underlying metals from further oxidation. Such properties should be examined to provide further mechanistic understanding of oxidation phenomena. This paper presents a novel method for determining the mechanical properties of material at the two sides of the metal-oxide (M/O) interface. It is applied to Zircaloy-2 cladding from a boiling water reactor. Two samples irradiated for 3 and 9 years have been examined. Micropillars were fabricated in the vicinity of M/O interface in the oxide, metal, and transition region using focused ion beam (FIB). The pillars were then uniaxially compressed using nano-indentation. Results prove the ability to pinpoint and consistently measure Young's modulus and yield strength of specific regions around the M/O interface. The Young's modulus and yield strength of metal and oxide regions for the two Zircaloy-2 samples are reported.
引用
收藏
页码:842 / 850
页数:9
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