期刊
CORROSION SCIENCE
卷 86, 期 -, 页码 108-122出版社
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.corsci.2014.04.041
关键词
Alloy 600; Stress corrosion; Internal oxidation; Selective oxidation; STEM
资金
- University Network of Excellence in Nuclear Engineering (UNENE)
- Natural Sciences and Engineering Research Council of Canada (NSERC)
- Nuclear Ontario, an ORF-RE
- McMaster University
- NSERC
Alloy 600 in the solution annealed (SA) and thermally treated (TT) conditions was exposed to a hydrogenated steam environment considered to simulate primary water in pressurized water reactors. The likely susceptibility to primary water stress corrosion cracking (PWSCC) was evaluated using the internal oxidation model. A FIB was used to extract cross-sections from Alloy 600 samples and elemental maps were generated; internal oxidation was observed intragranularly in all cases, resulting in expulsion of metallic nickel to the surface. Intergranular oxidation and embrittlement was observed in SA samples, while a thick and dense Cr-rich oxide was formed intergranularly on TT samples. (C) 2014 Elsevier Ltd. All rights reserved.
作者
我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。
推荐
暂无数据