Effect of strain-path on stress corrosion cracking of AISI 304L stainless steel in PWR primary environment at 360 °C

Couvant, Thierry; Vaillant, François Le; Boursier, J.M.

doi:10.1533/9781845693466.2.87

Cited by 13 publications

(15 citation statements)

References 7 publications

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“…The deleterious effect of cross tests on susceptibility of 304 L to IGSCC in PWR environments (1,000 ppm B, 2 ppm Li, 20 cc H 2 ) at 360 °C was shown in previous studies [46]. This result has been interpreted by the authors to be a consequence of the strain localization induced by orthogonal strain paths as defined by Schmitt [47].…”

Section: Resultsmentioning

confidence: 56%

See 1 more Smart Citation

Using Microscopy to Help with the Understanding of Degradation Mechanisms Observed in Materials of Pressurized Water Reactors

Legras¹,

Volgin²,

Radiguet³

et al. 2017

JMSE-B

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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 microscopies and of their last improvements up to the promising possibilities of monochromated and aberrations corrected TEM/STEM. A specific focus is placed on four different degradation mechanisms observed in austenitic stainless steel: irradiation ageing, corrosion fatigue, stress corrosion cracking and corrosion.

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Section: Resultsmentioning

confidence: 56%

“…Many factors affecting corrosion rate and cracks growth were studied by several authors [74][75][76][77][78][79][80][81][82][83]. Nevertheless, the contribution of the oxide layers themselves remains crucial and is still suffering from a lack of understanding.…”

Section: State Of the Artmentioning

confidence: 99%

Using Microscopy to Help with the Understanding of Degradation Mechanisms Observed in Materials of Pressurized Water Reactors

Legras¹,

Volgin²,

Radiguet³

et al. 2017

JMSE-B

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“…Many studies have been conducted on nonsensitized stainless steels to investigate the influences of various parameters, such as water chemistry, material composition and stress, on the initiation and growth of SCC and to elucidate SCC mechanisms. [1][2][3][4][5][6][7][8][9][10][11][12] With respect to SCC in hydrogenated high-temperature water relevant to PWR primary water, referred to as low-potential SCC (LPSCC), effects of chromium content in materials and dissolved hydrogen have recently been reported by Arioka et al 12) The chromium content in materials has a beneficial effect on LPSCC susceptibility, whereas dissolved hydrogen accelerates LPSCC based on the constant extension rate technique (CERT) results. Since water chemistry and material composition influence both SCC susceptibility and corrosion behavior, the mechanism of SCC is considered to be inevitably related to corrosion behavior.…”

Section: Introductionmentioning

confidence: 99%

Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water—Effect of Chromium Content in Alloys and Dissolved Hydrogen—

Terachi

Yamada²,

Miyamoto³

et al. 2008

Journal of Nuclear Science and Technology

131

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The structure and composition of surface oxide films on austenitic stainless steels in hydrogenated high-temperature water were examined by changing the chromium content in alloys and the concentration of dissolved hydrogen in high-temperature water. Auger electron spectroscopy, X-ray diffraction and analytical transmission electron microscopy revealed that the oxide films had a double-layer structure: ironbased spinels as the outer layer and chromium-rich spinel oxide as the inner layer. Increasing the chromium content suppressed the corrosion rate and produced fine oxide particles with a higher chromium concentration in the inner layer. Increasing the concentration of dissolved hydrogen enhanced the corrosion rate without a notable change in oxide structure. These influences are considered to originate from changes in cation diffusion through the inner layer, such as a decrease in the lattice diffusion of iron in the inner layer due to a higher concentration of chromium in the oxide as a diffusion barrier for a high chromium content in the alloys and due to a lower oxygen partial pressure for a higher concentration of dissolved hydrogen.

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“…Based on the SCC statistics identified in the French PWRs by Couvant et al [1], most of the cases were identified after a period of at least of 50000 hours. Literature results also indicate that the water chemistry [9][10][11], testing temperature [12], degree and paths of pre-strain [9,10,13,14] and surface finish [15][16][17] and heat treatment are the main factors that influence SCC. Furthermore, when austenitic stainless steels are exposed to high temperature water, a double layer structured oxide layer forms, which consists of a fine grained, compact, and chromium-rich inner oxide layer Kruska et al and Lozano-Perez suggest that the oxidation which preferentially occurs along the grain boundaries and slip bands could be one of the possible reasons for the occurrence of SCC.…”

Section: Introductionmentioning

confidence: 99%

Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water

Scenini

Lindsay

Chang

et al. 2017

The Minerals, Metals &Amp; Materials Series

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Slow strain rate tensile (SSRT) tests were conducted on conventional and tapered samples manufactured from forged Type 304L stainless steel to assess the stress corrosion cracking (SCC) behaviour in simulated PWR primary water. Several testing and microstructural parameters were investigated in order to explore the conditions under which crack initiation might occur. Surface preparation appeared to play a very important role on SCC initiation whereby the machined surfaces were the least susceptible to SCC initiation whilst oxide polishing suspension (OPS) polished surfaces were more susceptible. On the machined surfaces the cracks were always transgranular (TG) in nature and associated with the machining marks. Conversely, on fine polished surfaces with oxide polishing suspension the crack morphology was mainly intergranular in nature, although minor transgranular cracking was observed. The regions in the proximity of the ferrite/austenite interface were shown to be very susceptible to SCC initiation especially on the OPS polished surfaces and this was attributed to the strain localization upon dynamic deformation. Furthermore, intragranular inclusions appeared to dissolve and act as initiation sites for transgranular cracking to occur. The roles of strain rate, dynamic deformation and microstructure on the initiation of SCC are also discussed.

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Effect of strain-path on stress corrosion cracking of AISI 304L stainless steel in PWR primary environment at 360 °C

Cited by 13 publications

References 7 publications

Using Microscopy to Help with the Understanding of Degradation Mechanisms Observed in Materials of Pressurized Water Reactors

Using Microscopy to Help with the Understanding of Degradation Mechanisms Observed in Materials of Pressurized Water Reactors

Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water—Effect of Chromium Content in Alloys and Dissolved Hydrogen—

Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water

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