Influence of Dissolved Hydrogen on Oxide Film and PWSCC of Alloy 600 in PWR Primary Water
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概要
- 論文の詳細を見る
In order to investigate the influence of dissolved hydrogen on the oxide film and primary water stress corrosion cracking (PWSCC) of Alloy 600 in primary water of PWR under actual operating temperature range, electrochemical polarization measurement, analysis of the oxide film on the alloy and PWSCC test were carried out. In all cases, the content of dissolved hydrogen was changed from 0 to 45 cc/kg H2O. The anodic polarization curve reveals that the peak current density increases with increasing dissolved hydrogen and the change of the peak current density becomes maximum between 11 and 30 cc/kg H2O of dissolved hydrogen. According to the results of oxide film analysis, it is seen that the oxide films formed below 11 cc/kg H2O of dissolved hydrogen are relatively thick and rich in Ni, but those formed at higher dissolved hydrogen content are relatively thin and rich in Cr and Fe. The susceptibility of the alloy to PWSCC has a peak at 11 cc/kg H2O of dissolved hydrogen, which reveals that the property of the oxide film may play important role in PWSCC of alloy.
- 一般社団法人 日本原子力学会の論文
- 2003-01-25
著者
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Totsuka Nobuo
Material Aging Project Institute Of Nuclear Safety System Inc.
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Terachi T
Material Aging Project Institute Of Nuclear Safety System Inc.
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TERACHI Takumi
Material Aging Project, Institute of Nuclear Safety System, Inc.
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NAKAGAWA Tomokazu
Mihama Nuclear Power Station Office, The Kansai Electric Power Co., Inc.
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NAKAJIMA Nobuo
Material Aging Project, Institute of Nuclear Safety System, Inc.
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Nakagawa Tomokazu
Mihama Nuclear Power Station Office The Kansai Electric Power Co. Inc.
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Nakajima Nobuo
Material Aging Project Institute Of Nuclear Safety System Inc.
関連論文
- Development of an Autoclave with Zirconia Windows for In-situ Observation of Sample Surface under the Primary Water Conditions of Pressurized Water Reactors
- Influence of Dissolved Hydrogen on Structure of Oxide Film on Alloy 600 Formed in Primary Water of Pressurized Water Reactors
- Influence of Dissolved Hydrogen on Oxide Film and PWSCC of Alloy 600 in PWR Primary Water
- Influence of Dissolved Hydrogen on Structure of Oxide Film on Alloy 600 Formed in Primary Water of Pressurized Water Reactors