Stress Corrosion Cracking Behavior of Zirconium in Boiling Nitric Acid Solutions at Oxide Formation Potentials
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- Ishijima Yasuhiro
- Japan Atomic Energy Agency
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- Kato Chiaki
- Japan Atomic Energy Agency
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- Motooka Takafumi
- Japan Atomic Energy Agency
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- Yamamoto Masahiro
- Japan Atomic Energy Agency
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- Kano Yoichi
- Japan Nuclear Fuel Limited
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- Ebina Tetsunari
- Japan Nuclear Fuel Limited
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Zirconium has been utilized in nuclear fuel reprocessing plants because of its superior corrosion resistance in nitric acid solutions. However, stress corrosion cracking (SCC) susceptibility of zirconium has been reported in boiling nitric acid solutions at the passivity breakdown potential. However, it has not been clear the SCC initiation and propagation behavior of zirconium.<BR>In this study, to clarify the SCC initiation and propagation behavior of zirconium, constant load tensile tests were carried out in boiling nitric acid solutions.<BR>From the results, many cracks were initiated under the oxide film and maximum crack led to rupture in the potentials that nobler than passivity breakdown potential. These results showed that the SCC of zirconium in boiling nitric acid solutions is due to the oxide formation. And this SCC behavior suggests that the SCC behavior of zirconium can be attributed to tarnish rupture model.
収録刊行物
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- MATERIALS TRANSACTIONS
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MATERIALS TRANSACTIONS 54 (6), 1001-1005, 2013
公益社団法人 日本金属学会
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詳細情報 詳細情報について
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- CRID
- 1390001204251776768
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- NII論文ID
- 10031176424
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- NII書誌ID
- AA1151294X
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- COI
- 1:CAS:528:DC%2BC3sXht1Wgu7jL
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- ISSN
- 13475320
- 13459678
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- NDL書誌ID
- 024524776
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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
- NDL
- Crossref
- CiNii Articles
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- 使用不可