Title of article :
Corrosion of Alloy 617 in high-temperature gas environments
Author/Authors :
Yeh، نويسنده , , Tsung-Kuang and Chang، نويسنده , , Hao-Ping and Wang، نويسنده , , Mei-Ya and Yuan، نويسنده , , Trai and Kai، نويسنده , , Ji-Jung، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2014
Pages :
5
From page :
257
To page :
261
Abstract :
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 O2, can interact with structural materials at working temperatures of >900 °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 O2 and H2O. A series of general corrosion tests were conducted at test temperatures of 650 °C, 750 °C, 850 °C and 950 °C under various coolant compositions of dry air, 1% O2, 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.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2014
Journal title :
Nuclear Engineering and Design Eslah
Record number :
1594425
Link To Document :
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