Influence of Dissolved Hydrogen on Structure of Oxide Film on Alloy 600 Formed in Primary Water of Pressurized Water Reactors
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概要
- 論文の詳細を見る
In order to investigate the relationship between the susceptibility of primary water stress corrosion cracking (PWSCC) in Alloy 600 and the content of dissolved hydrogen (DH) in the primary water of pressurized water reactors (PWR), structural analysis of oxide films formed under four different DH conditions in simulated primary water of PWR was carried out using a grazing incidence X-ray diffractometer (GIXRD), a scanning electron microscope (SEM) and a transmission electron microscope (TEM). In particular, to perform accurate analysis of the thin oxide films, the synchrotron radiation of SPring-8 was used for GIXRD.It has been observed that the oxide film is mainly composed of nickel oxide, under the condition without hydrogen. On the other hand, needle-like oxides are formed at 1.0 ppm of DH. In the environment of 2.75 ppm of DH, the oxide film has thin spinel structures. From these results and phase diagram consideration, the condition around 1.0 ppm of DH corresponds to the boundary between stable NiO and spinel oxides, and also to the peak range of PWSCC susceptibility. This suggests that the boundary between NiO and spinel oxides may affect the SCC susceptibility.
- 社団法人 日本原子力学会の論文
- 2003-07-25
著者
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Totsuka Nobuo
Material Aging Project Institute Of Nuclear Safety System Inc.
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Yamada Takuyo
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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DEGUCHI Hiroshi
Technical Research Center, The Kansai Electric Power Co., Inc.
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HORIUCHI Masaki
Kanden Kakou Co., Ltd.
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OSHITANI Masato
Kanden Kakou Co., Ltd.
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Oshitani Masato
Kanden Kakou Co. Ltd.
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Deguchi Hiroshi
Technical Research Center The Kansai Electric Power Co. Inc.
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Horiuchi Masaki
Kanden Kakou Co. Ltd.
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Nakagawa Tomokazu
Mihama Nuclear Power Station Office The Kansai Electric Power Co. 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