Corrosion of Alloy 617 in high-temperature gas environments

被引:18
|
作者
Yeh, Tsung-Kuang [1 ,2 ]
Chang, Hao-Ping [1 ]
Wang, Mei-Ya [3 ]
Yuan, Trai [1 ]
Kai, Ji-Jung [1 ,2 ]
机构
[1] Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Hsinchu 300, Taiwan
[2] Natl Tsing Hua Univ, Dept Engn & Syst Sci, Hsinchu 300, Taiwan
[3] Natl Tsing Hua Univ, Nucl Sci & Technol Dev Ctr, Hsinchu 300, Taiwan
关键词
WATER-VAPOR; OXIDATION BEHAVIOR; ALUMINUM; OXIDES; 304L;
D O I
10.1016/j.nucengdes.2013.11.045
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
High-temperature gas-cooled reactors (HTGRs) with helium gas as the primary coolant have been considered as one type of the Generation IV nuclear power reactor systems. Several nickel-based superalloys, including Alloy 617, are potential structural materials to serve as pressure boundary components, such as the intermediate heat exchanger (IHX) in an HTGR. Impurities in a helium coolant, such as H2O and O-2, can interact with structural materials at working temperatures of >900 degrees C, leading to serious degradation on these materials. In addition, defects in IHX surface coatings would allow these species to reach and interact with the external surfaces of these components, leading to similar or even more serious degradation. In this study we investigated the oxidation behavior of Alloy 617 in high-temperature, gaseous environments with various levels of O-2 and H2O. A series of general corrosion tests were conducted at test temperatures of 650 degrees C, 750 degrees C, 850 degrees C and 950 degrees C under various coolant compositions of dry air, 1% O-2, 10% relative humidity (RH), and 50% RH. Preliminary results showed that the surface morphologies of the Alloy 617 samples exhibited distinct evidence of intergranular corrosion. Compact chromium oxide layers were observed on the sample surfaces. The oxidation mechanisms of this alloy in the designated environments are discussed. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:257 / 261
页数:5
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