Corrosion Resistance and Surface Treatment of Nuclear Fuel Elements

Zirconium alloys (Zircaloy-2 and -4) covering nuclear fuels corrode in high-temperature cooling water of a nuclear reactor. The mechanisms of corrosion in a boiling water reactor and a pressurized water reactor are explained separately, considering the effects of radiation and hydrogen. To improve t...

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Bibliographic Details
Published inHyōmen gijutsu Vol. 40; no. 2; pp. 287 - 292
Main Author OGATA, Keizo
Format Journal Article
LanguageEnglish
Japanese
Published Tokyo The Surface Finishing Society of Japan 01.01.1989
Japan Science and Technology Agency
Subjects
Corrosion
Nuclear Fuel
Surface Treatment
Zirconium Alloy
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Summary:Zirconium alloys (Zircaloy-2 and -4) covering nuclear fuels corrode in high-temperature cooling water of a nuclear reactor. The mechanisms of corrosion in a boiling water reactor and a pressurized water reactor are explained separately, considering the effects of radiation and hydrogen. To improve the corrosion resistance, various types of surface treatments (physical and chemical polishing, anodic oxidation, coating, etc.) and modification of the composition (to change the crystal structure, precipitation behavior, etc.) have been attempted. These factors must be evaluated by long-term irradiation tests. 29 ref.--H.O.
Bibliography:ObjectType-Article-2
SourceType-Scholarly Journals-1
ObjectType-Feature-1
content type line 23
ISSN:0915-1869
1884-3409
DOI:10.4139/sfj.40.287