Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water : Effect of Chromium Content in Alloys and Dissolved Hydrogen
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概要
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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.
- 2008-10-01
著者
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TERACHI Takumi
Institute of Nuclear Safety System, Inc.
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YAMADA Takuyo
Institute of Nuclear Safety System, Inc.
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MIYAMOTO Tomoki
Institute of Nuclear Safety System, Inc.
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ARIOKA Koji
Institute of Nuclear Safety System, Inc.
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FUKUYA Koji
Institute of Nuclear Safety System, Inc.
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Fukuya Koji
Institute Of Nuclear Safety System Inc.
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Fukuya Koji
Institute Of Nuclear Safety System
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Arioka Koji
Institute Of Nuclear Safety System Inc.
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Yamada Takuyo
Institute Of Nuclear Safety System Inc.
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Terachi Takumi
Institute Of Nuclear Safety System Inc.
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Miyamoto Tomoki
Institute Of Nuclear Safety System Inc.
関連論文
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