Effect of irradiation defects on the work hardening behavior

Pokor, C.; Averty, X.; Bréchet, Y.; Dubuisson, Philippe; Massoud, J.P.

doi:10.1016/j.scriptamat.2003.11.029

Cited by 37 publications

(39 citation statements)

References 12 publications

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“…In this study a mean foil thickness of 100 nm has been taken to estimate the density of loops. This value is in agreement with several others studies where similar materials have been characterized [19,33,34]. The error in number density reported in this paper takes into account the uncertainty associated to the TEM foils thickness.…”

Section: Microstructure Characterizationsupporting

confidence: 93%

“…With increasing dose, a slight increase in average number density and diameter of Frank loops was observed in iron irradiated samples. The saturation in the Frank loop density and diameter observed for the 7 dpa sample seems consistent with the saturation in Frank loop density and size, reported in neutron [4,36,39] and ion irradiated samples [19,20,22,23,40] around 1 dpa and 5 dpa, respectively. Frank loop density was notably higher in proton irradiated sample compared to the iron irradiated samples despite a smaller irradiation dose in the former.…”

Section: Microstructuresupporting

confidence: 89%

“…The number density and mean size of Frank loops obtained for both iron and proton irradiated samples were in accordance with the values reported in neutron [10,18,38,39] and ion literature [18e23]. With increasing dose, a slight increase in average number density and diameter of Frank loops was observed in iron irradiated samples.…”

Section: Microstructuresupporting

confidence: 88%

“…A first approximation of the hardening induced by the irradiation induced defects can be obtained based on the barrier hardening model [46] which correlates the increase in yield strength (Ds y ) with density of irradiation induced defects as given by equation (2).…”

Section: Correlation Between Irradiation Hardening and Microstructuramentioning

confidence: 99%

See 3 more Smart Citations

Characterization of ion irradiation effects on the microstructure, hardness, deformation and crack initiation behavior of austenitic stainless steel:Heavy ions vs protons

Gupta

Hure

Tanguy

et al. 2018

Journal of Nuclear Materials

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OATAO is an open access repository that collects the work of Toulouse researchers and makes it freely available over the web where possible. This is an author-deposited version published in : http://oatao. Proton irradiation is generally used as a representative alternative of neutron irradiation to improve the current understanding of the mechanisms involved in IASCC. This study assesses the possibility of using heavy ions irradiation to evaluate IASCC mechanisms by comparing the irradiation induced modifications (in microstructure and mechanical properties) and cracking susceptibility of SA 304 L after both type of irradiations: Fe irradiation at 450 C and proton irradiation at 350 C. Irradiation-induced defects are characterized and quantified along with nano-hardness measurements, showing a correlation between irradiation hardening and density of Frank loops that is well captured by Orowan's formula. Both irradiations (iron and proton) increase the susceptibility of SA 304 L to intergranular cracking on subjection to Constant Extension Rate Tensile tests (CERT) in simulated nominal PWR primary water environment at 340 C. For these conditions, cracking susceptibility is found to be quantitatively similar for both irradiations, despite significant differences in hardening and degree of localization.

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Section: Microstructure Characterizationsupporting

confidence: 93%

Section: Microstructuresupporting

confidence: 89%

Section: Microstructuresupporting

confidence: 88%

Section: Correlation Between Irradiation Hardening and Microstructuramentioning

confidence: 99%

See 2 more Smart Citations

Characterization of ion irradiation effects on the microstructure, hardness, deformation and crack initiation behavior of austenitic stainless steel:Heavy ions vs protons

Gupta

Hure

Tanguy

et al. 2018

Journal of Nuclear Materials

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show abstract

“…The irradiation defects visible in TEM are interstitial Frank loops with a typical density between 0.2 and 1.0 10 23 m −3 and a mean diameter between 6 and 12 F o r P e e r R e v i e w O n l y 2 nm, depending on the material and the irradiation conditions. With irradiation, the SS316 and SS304 yield stress increases from ∼300 MPa up to ∼800 MPa at 300 K [20][21][22]. Two deformation modes are observed in irradiated SS, depending on the temperature.…”

mentioning

confidence: 99%