Mechanism of irradiation assisted stress corrosion crack initiation in thermally sensitized 304 stainless steel

Onchi, Takeo; Dohi, Kenji; Soneda, Naoki; Navas, M.; Castaño, María

doi:10.1016/j.jnucmat.2004.11.012

Cited by 43 publications

(23 citation statements)

References 8 publications

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“…[1][2][3] Among these radiation-induced changes, the importance of deformation mode on IASCC has been emphasized. [3][4][5] High-density defect clusters such as dislocation loops produced by neutron irradiation hinder the movement of dislocations. As the dislocation moves, it annihilates the defects on the slip plane, thus opening up a path for subsequent dislocations, which is called a dislocation channel.…”

Section: Introductionmentioning

confidence: 99%

Deformation Structure in Highly Irradiated Stainless Steels

Nishioka¹,

Fukuya²,

Fujii³

et al. 2008

J. Nucl. Sci. Technol.

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Surface steps and deformation microstructure in cold-worked SUS316 stainless steels irradiated to 4 and 35 dpa (displacements per atom) were examined after being deformed by uniaxial tensile stress at 320 C at a slow or fast strain rate. Dislocation channeling was the predominant mode of deformation near the surface at the slow strain rate. Twinning was dominant at the fast strain rate whereas twinning and nanotwin formation occurred in the locally stressed area at the slow strain rate. Deformation heterogeneity measured using the spacing of coarse surface steps induced by dislocation channels increased with increasing dose from 4 to 35 dpa. Grain boundary separation occurred when dislocation pileups and high normal stress on the grain boundary plane coexisted, which likely was a precursor of intergranular cracking without any environmental factor.

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Section: Introductionmentioning

confidence: 99%

Deformation Structure in Highly Irradiated Stainless Steels

Nishioka¹,

Fukuya²,

Fujii³

et al. 2008

J. Nucl. Sci. Technol.

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“…Although all these factors are important for IASCC degradation, none appear to be the primary cause and the issue is still open. Recent works [7][8][9][10][11] identify plastic strain localization as another important contributing factor of IASCC. Onchi et al [8] suggested that crack initiation in sensitized 304 SS may be linked to the presence of deformation bands.…”

Section: Introductionmentioning

confidence: 99%

“…Recent works [7][8][9][10][11] identify plastic strain localization as another important contributing factor of IASCC. Onchi et al [8] suggested that crack initiation in sensitized 304 SS may be linked to the presence of deformation bands. Jiao et al [9] correlated different stacking fault energy (SFE) values (related to the propensity towards strain localization, in stainless steel irradiated to up to 5 dpa) to their intergranular percentage on the fracture surface in constant extension rate tensile (CERT) tests conducted under an argon atmosphere at 288°C.…”

Section: Introductionmentioning

confidence: 99%

“…For austenitic stainless steels, localization may be characterized by channelling (high doses, high temperature and low stain rate) and twinning (low doses, low temperature and high stain rate). Onchi et al [7,8] also suggested that the intersection between dislocation channels and grain boundaries constitutes a high concentration stress and strain area, leading to a preferential crack initiation area. Given this, it could be useful to understand how oxide species grow on the surface of specimens with localized deformation bands, in other words if in static conditions, localized deformation bands may be considered as preferential sites for oxide growth.…”

Section: Introductionmentioning

confidence: 99%

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Influence of localized plasticity on oxidation behaviour of austenitic stainless steels under primary water reactor

Cissé

Laffont

Lafont

et al. 2013

Journal of Nuclear Materials

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International audienceThe sensitivity of precipitation-strengthened A286 austenitic stainless steel to stress corrosion cracking was studied by means of slow-strain-rate tests. First, alloy cold working by low cycle fatigue (LCF) was investigated. Fatigue tests under plastic strain control were performed at different strain levels (Δεp/2 = 0.2%, 0.5%, 0.8% and 2%) to establish correlations between stress softening and the deformation microstructure resulting from the LCF tests. Deformed microstructures were identified through TEM investigations. The interaction between oxidation and localized deformation bands was also studied and it resulted that localized deformation bands are not preferential oxide growth channels. The pre-cycling of the alloy did not modify its oxidation behaviour. However, intergranular oxidation in the subsurface under the oxide layer formed after exposure to PWR primary water was shown

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“…[1][2][3][4][5][6] In general, slip band formation and growth, microcrack initiation, and macrocrack propagation are supposed to occur under the cyclic loading of fatigue. Therefore, fatigue behavior, especially microcrack initiation behavior following slip band formation and growth, is believed to be significantly affected by the localized deformation accompanied by coarse slip in the irradiated austenitic stainless steel.…”

Section: Introductionmentioning

confidence: 99%

Fatigue Crack Initiation in Proton-Irradiated Austenitic Stainless Steel

Nogami

Sato

Hasegawa

2011

Journal of Nuclear Science and Technology

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The effect of irradiation on slip band formation and growth and microcrack initiation behavior under low cycle fatigue in SUS316L austenitic stainless steel was investigated using accelerator-based proton irradiation and a low cycle fatigue test at room temperature in air. The mean space of the slip line in proton-irradiated specimens was 25-40% wider than that in unirradiated specimens under the same number of cycles, possibly due to localized deformation by proton irradiation. The microcrack initiation life of the proton-irradiated specimens was approximately 20% of that of the unirradiated specimens. While the microcrack initiation in the unirradiated specimens was observed at the grain boundary, twin boundary, slip band, and triple junction, that in the proton-irradiated specimens was observed only at the twin boundary and slip band, possibly due to irradiation hardening. The step-height of an extrusion near the microcrack was almost the same in the unirradiated and proton-irradiated specimens regardless of the initiation site (100-150 nm). Therefore, the microcrack initiation was considered to occur when the surface morphology change involving the extrusion exceeded the specific threshold value.

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Mechanism of irradiation assisted stress corrosion crack initiation in thermally sensitized 304 stainless steel

Cited by 43 publications

References 8 publications

Deformation Structure in Highly Irradiated Stainless Steels

Deformation Structure in Highly Irradiated Stainless Steels

Influence of localized plasticity on oxidation behaviour of austenitic stainless steels under primary water reactor

Fatigue Crack Initiation in Proton-Irradiated Austenitic Stainless Steel

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