2017
DOI: 10.17265/2161-6221/2017.9-10.002
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Using Microscopy to Help with the Understanding of Degradation Mechanisms Observed in Materials of Pressurized Water Reactors

Abstract: Abstract:Even if temperature, pressure and chemistry of the cooling water are not very high and aggressive, materials used in PWRs (Pressurized Water Reactors) are exposed to different degradation mechanisms. One of the main goals of the research programs in this field is to develop physical model of the mechanisms down to the atomic scale. Such approach needs a clear description and understanding of the degradation mechanisms at the same small scale. This paper illustrates the benefits of different microscopi… Show more

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Cited by 2 publications
(3 citation statements)
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“…Therefore, our TEM analysis revealed the presence of irradiation defects (Frank loops and cavities) in the 316 L alloy induced by the proton irradiation. Similar intragranular segregation on irradiation defects was already evidenced by Atom Probe Tomography (APT) [27][28][29] in agreement with our results. To the author knowledge, solely Edwards et al [26] and Fukuya et al [30] reported segregation on voids or dislocations using TEM but did not present any imaging of it.…”
Section: Radiation Induced Segregation On Irradiation Defectssupporting
confidence: 93%
See 1 more Smart Citation
“…Therefore, our TEM analysis revealed the presence of irradiation defects (Frank loops and cavities) in the 316 L alloy induced by the proton irradiation. Similar intragranular segregation on irradiation defects was already evidenced by Atom Probe Tomography (APT) [27][28][29] in agreement with our results. To the author knowledge, solely Edwards et al [26] and Fukuya et al [30] reported segregation on voids or dislocations using TEM but did not present any imaging of it.…”
Section: Radiation Induced Segregation On Irradiation Defectssupporting
confidence: 93%
“…15) would increase the grain boundary sensitivity, resulting in higher corrosion susceptibility. Terachi et al [27] previously reported that the oxidation kinetic is linked to the alloy chromium content. The less chromium in the alloy, the more oxidation is promoted.…”
Section: Effect O F I Rradiation O N T He G Rain B Oundary Oxidationmentioning
confidence: 99%
“…The PWR water environment can facilitate the crack initiation by successive repetition of oxidation of the strain concentration site, and rupture of the oxide film formed on the crack tip, as previously pointed out. 19,44 Nevertheless, it is worth noticing that these interactions are based on the assumption of a sufficient accumulation of plastic strain required to promote preferential oxidation 19,43,45 and to conduct to the failure of the oxide layer by shearing. 43,44 Secondly, as concerns the crack propagation life as quantified by the N a0!2950μm parameter, the PWR water evidently reduces the crack propagation life, as indicated in Figure 9B.…”
Section: Effect Of Pwr Water On Fatigue Lifementioning
confidence: 99%