Published October 2008 | Version v1
Journal article

Corrosion behavior of stainless steels in simulated PWR primary water. Effect of chromium content in alloys and dissolved hydrogen

  • 1. Institute of Nuclear Safety System, Inc., Mihama, Fukui (Japan)

Description

The structure and composition of surface oxide films on austenitic stainless steels in hydrogenated high-temperature water were examined by changing the chromium content in alloys and the concentration of dissolved hydrogen in high-temperature water. Auger electron spectroscopy, X-ray diffraction and analytical transmission electron microscopy revealed that the oxide films had a double-layer structure: iron-based spinels as the outer layer and chromium-rich spinel oxide as the inner layer. Increasing the chromium content suppressed the corrosion rate and produced fine oxide particles with a higher chromium concentration in the inner layer. Increasing the concentration of dissolved hydrogen enhanced the corrosion rate without a notable change in oxide structure. These influences are considered to originate from changes in cation diffusion through the inner layer, such as a decrease in the lattice diffusion of iron in the inner layer due to a higher concentration of chromium in the oxide as a diffusion barrier for a high chromium content in the alloys and due to a lower oxygen partial pressure for a higher concentration of dissolved hydrogen. (author)

Additional details

Identifiers

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo)
Journal Volume
45
Journal Issue
10
Journal Page Range
p. 975-984
ISSN
0022-3131

Optional Information

Notes
Available from doi: http://dx.doi.org/10.3327/jnst.45.975; 31 refs., 18 figs., 2 tabs.