Oxide growth and dissolution on 316L stainless steel during irradiation in high temperature water

被引：34
|
作者：
Hanbury, Rigel D. [1 ]
Was, Gary S. [1 ]
机构：
[1] Univ Michigan, 2355 Bonisteel Blvd, Ann Arbor, MI 48109 USA
来源：
CORROSION SCIENCE | 2019年 / 157卷
关键词：
Stainless steel; Ion implantation; TEM; STEM; Reactor conditions; ELECTROCHEMICAL-BEHAVIOR; ACCELERATED CORROSION; HYDROGEN-PEROXIDE; RADIATION; RADIOLYSIS; OXIDATION;
D O I：
10.1016/j.corsci.2019.06.006
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Helium was implanted in 316L stainless steel to produce a marker layer of bubbles to provide a reference for the assessment of oxidation and dissolution during proton irradiation in 320 degrees C hydrogenated water for 24 h and 72 h. Inner oxide thickness characterized by TEM dropped by a factor of 4.5 with irradiation. Marker layer measurements reveal a factor of 3 lower metal loss with irradiation. Metal loss increased without inner oxide growth between 24 h and 72 h of irradiation. Greater enrichment of chromium in the oxide under irradiation yields a more protective oxide film despite evidence of oxide dissolution.
引用
收藏
页码：305 / 311
页数：7
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