Hydrogen absorption associated with the corrosion mechanism of 316L stainless steels in primary medium of Pressurized Water Reactor (PWR)
Source abstract
Abstract
Samples of 316L were exposed at 325 degrees C to PWR primary water labelled with deuterium and oxygen 18. The SIMS and GD-OES analysis has revealed the presence of deuterium in the internal oxide layer and in the underlying alloy. Two-stage corrosion experiments have shown that the oxygen and hydrogen transport in the oxide layer is not coupled and that the short-circuit diffusion coefficient of O-18 in the oxide scale: D-sc = (9 +/- 1).10(-17) cm(2) s(-1). These results are used to propose a mechanism describing the anionic growth of the protective oxide layer and the concomitant adsorption of hydrogen in the alloy. (C) 2014 Elsevier Ltd. All rights reserved.
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Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Hydrogen embrittlement and corrosion behaviors in metals
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