Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors 1999
DOI: 10.1002/9781118787618.ch25
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Stress Corrosion Life Assessment of Alloy 600 PWR Components

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Cited by 10 publications
(8 citation statements)
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“…There is a reasonably good agreement between different studies. The stress threshold of Alloy 182 is assumed to be close to the yield stress of the material [28,45,46], which is confirmed by our test results.…”
Section: Phase 2 -Ni-base Alloy 182supporting
confidence: 84%
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“…There is a reasonably good agreement between different studies. The stress threshold of Alloy 182 is assumed to be close to the yield stress of the material [28,45,46], which is confirmed by our test results.…”
Section: Phase 2 -Ni-base Alloy 182supporting
confidence: 84%
“…without any dynamic strain some materials may not fail. This is typically valid for Ni-base alloys in high-temperature water [26,27] Temperature: SCC is a thermally activated process, which is particularly true for Alloy 182 in high-temperature water [2,28 30]. With increasing temperature, the crack propagation increases significantly.…”
Section: Introductionmentioning
confidence: 99%
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“…Therefore, many researchers have endeavored to predict SCC initiation time for a given component. However, accurately predicting SCC initiation is difficult because the mechanism is quite complex and not yet clearly understood; instead, empirical SCC initiation models are generally considered [ 4 , 5 , 6 ].…”
Section: Introductionmentioning
confidence: 99%
“…However, this is a difficult task due to the complex mechanism of SCC initiation, which is not clearly identified yet. Therefore, empirical SCC initiation models are generally adopted for this purpose [ 4 , 5 , 6 ].…”
Section: Introductionmentioning
confidence: 99%