The environmental degradation behavior of FeNiMnCr high entropy alloy in high temperature hydrogenated water

被引：16

作者：

Dong, Jiuyang ^{[1
]}

Feng, Xingyu ^{[1
]}

Hao, Xianchao ^{[2
,3
]}

Kuang, Wenjun ^{[1
]}

机构：

[1] Xi An Jiao Tong Univ, Ctr Adv Mat Performance Nanoscale CAMP Nano, State Key Lab Mech Behav Mat, Xian 710049, Peoples R China

[2] Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China

[3] ChineseAcad Sci, Shi Changxu Innovat Ctr Adv Mat, Inst Met Res, Shenyang 110016, Peoples R China

来源：

SCRIPTA MATERIALIA | 2021年 / 204卷

基金：

中国国家自然科学基金;

关键词：

High entropy alloy; Oxidation; Corrosion; Scanning; transmission electron microscopy (STEM); Diffusion-induced grain boundary motion (DIGM); CORROSION; STABILITY;

D O I：

10.1016/j.scriptamat.2021.114127

中图分类号：

TB3 [工程材料学];

学科分类号：

0805 ; 080502 ;

摘要：

Co-free high entropy alloy (HEA) 28%Fe-27%Ni-27%Mn-18%Cr shows good irradiation resistance and could be a potential candidate for structural material in nuclear power industry. In this work, the environmental degradation behavior of this HEA was investigated in high temperature hydrogenated water. This HEA shows extensive intergranular cracking after constant extension rate tensile test, indicating that it is very susceptible to stress corrosion cracking (SCC) initiation. The microstructure analysis indicates that Mn and Cr diffuse outwards along the grain boundary during oxidation, inducing grain boundary migration. The Cr flux promotes the formation of Cr-enriched oxide layer above the grain boundary which prevents intergranular oxidation when the sample is unstressed. However, Mn is unstable in the oxide and tends to dissolve into the solution, making the oxide porous. The porous oxide fractures readily when stressed, inducing SCC initiation. (c) 2021 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.

引用

页数：6

共 24 条

[11] Neutron irradiation response of a Co-free high entropy alloy [J].