Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Rea 2011
DOI: 10.1007/978-3-319-48760-1_24
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Non-Linear Dynamics of the Morphology at the Oxide / Metal Interface of Austenitic Steels in Simulated Light Water Reactor Environments and its Implications for SCC Initiation

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“…The results of oxide film thickness were plotted in relation to weight gain/loss data of 316L and 316LN SS in Figure 13, which demonstrates particularly that the 316LN oxide film thickness increased while weight decreased. This implies that significant loss of alloying elements took place on 316LN under irradiation condition, which was discussed from an oxidation localization point of view in the reference [50]. Based upon the results outlined above, the observed behavior could be due to hydrogen formed by the transmutation of nitrogen in irradiated steels originating from the following transmutation [51]:…”
Section: Sem Observation-surface and Cross-sectionmentioning
confidence: 99%
“…The results of oxide film thickness were plotted in relation to weight gain/loss data of 316L and 316LN SS in Figure 13, which demonstrates particularly that the 316LN oxide film thickness increased while weight decreased. This implies that significant loss of alloying elements took place on 316LN under irradiation condition, which was discussed from an oxidation localization point of view in the reference [50]. Based upon the results outlined above, the observed behavior could be due to hydrogen formed by the transmutation of nitrogen in irradiated steels originating from the following transmutation [51]:…”
Section: Sem Observation-surface and Cross-sectionmentioning
confidence: 99%