Electrochemical Considerations Regarding General Corrosion of Materials in a BWR Primary Circuit.
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- HEMMI Yukio
- Nuclear Engineering Laboratory, Toshiba Corp.
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- ICHIKAWA Nagayoshi
- Nuclear Engineering Laboratory, Toshiba Corp.
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- SAITO Norihisa
- Nuclear Engineering Laboratory, Toshiba Corp.
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- MASUDA Takahisa
- Energy System Group, Toshiba Corp.
抄録
Electrochemical calculations of 3d-transition metal (Fe, Ni, Co and Cr)-water systems at 558 K were performed to evaluated the general corrosion behavior of materials in a BWR primary circuit. Thermodynamics expressed by Pourbaix diagrams, the solubilities of oxides and the equilibrium activities of H2, O2 and H2O2 in oxide formations, and kinetics determining the corrosion potential and corrosion rate of the materials were evaluated. The results assist recognition of the following corrosion behaviors:<BR>(1) Good corrosion resistance of type 304 SS under various water chemistry conditions is due to the properties of NiFe2O4 and (Fe, Ni)Cr2O4 ; namely wide stable regions and low diffusion coefficients of metal ions and the ability of these oxides to compensate for each others weakness.<BR>(2) A typical increase of the corrosion rate of Alloy X750 and Stellite #6 in an oxygenated aqueous environment containing H2O2 is due to the properties of NiO and CoO ; namely high solubilities and high diffusion coefficients of metal ions.
収録刊行物
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- Journal of Nuclear Science and Technology(日本原子力学会英文論文誌)
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Journal of Nuclear Science and Technology(日本原子力学会英文論文誌) 31 (11), 1202-1213, 1994
一般社団法人 日本原子力学会
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詳細情報 詳細情報について
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- CRID
- 1390001204095429760
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- NII論文ID
- 130000825572
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- COI
- 1:CAS:528:DyaK2MXitlChsLo%3D
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- ISSN
- 18811248
- 00223131
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可