Corrosion of 316L stainless steel in high temperature water and steam: effects of simultaneous proton irradiation

被引:1
作者
Hanbury, Rigel D. [1 ]
Was, Gary S. [2 ]
机构
[1] Bettis Atom Power Lab, 814 Pittsburgh McKeesport Blvd, West Mifflin, PA 15122 USA
[2] Univ Michigan, Nucl Engn & Radiol Sci, 2301 Bonisteel Blvd, Ann Arbor, MI 48109 USA
关键词
Stainless steel; STEM; Corrosion; Proton irradiation; PWR PRIMARY WATER; OXIDE-FILM; IN-SITU; RADIATION; DIFFUSION; OXIDATION; HYDROGEN; RELEASE; ALLOYS; DISSOLUTION;
D O I
10.1016/j.jnucmat.2024.155274
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
316L stainless steel was exposed to 320 degrees C hydrogenated water and 480 degrees C hydrogenated steam for 24 h and 72 h while simultaneously irradiated with 5.4 MeV protons to yield a damage rate of 7 x 10-7 dpa/s. Oxide films characterized in cross-section STEM revealed chemical and morphological differences. High levels of radiolysis in water resulted in significantly reduced corrosion rates while inducing dissolution of the inner oxide layer, whereas in steam the effects of radiolysis are insignificant. Conversely, displacement damage effects are negligible in water but significantly increase the corrosion rate in the steam condition through the growth of inner oxide porosity.
引用
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页数:17
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