Zirconium in the Nuclear Industry: Eighth International Symposium 1989
DOI: 10.1520/stp18871s
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A Systematic Survey of the Factors Affecting Zircaloy Nodular Corrosion

Abstract: Out-of-reactor corrosion tests in 10.3-MPa steam at temperatures between 490 and 530°C have been carried out on Zircaloy-2 tube specimens of various fabrication histories including archive specimens of the same tube lots as were used in the commercial boiling water reactor (BWR) to get data for comparison between in- and out-of-reactor nodular corrosion performances. Test conditions, such as temperature and duration, as well as material parameters, such as chemical composition, texture, and precipitates, were … Show more

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Cited by 9 publications
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