Microstructure of Au-ion irradiated 316L and FeNiCr austenitic stainless steels

Jublot-Leclerc S. 1 Li X. Legras L. Lescoat M.L. Fortuna F. 1 Gentils A. 1
1 CSNSM PS2 - Centre de Sciences Nucléaires et de Sciences de la Matière
Abstract : Thin foils of 316L were irradiated in situ in a Transmission Electron Microscope with 4 MeV Au ions at 450 °C and 550 °C. Similar irradiations were performed at 450 °C in FeNiCr. The void and dislocation microstructure of 316L is found to depend strongly on temperature. At 450 °C, a dense network of dislocation lines is observed in situ to grow from black dot defects by absorption of other black dots and interstitial clusters whilst no Frank loops are detected. At 550 °C, no such network is observed but large Frank loops and perfect loops whose sudden appearance is concomitant with a strong increase in void density as a result of a strong coupling between voids and dislocations. Moreover, differences in both alloys microstructure show the major role played by the minor constituents of 316L, increasing the stacking fault formation energy, and possibly leading to significant differences in swelling behaviour.
Keywords : Ion irradiation In situ TEM Austenitic stainless steel Dislocations Voids
Type de document :
Article dans une revue
Journal of Nuclear Materials, Elsevier, 2016, pp.436-446. 〈10.1016/j.jnucmat.2016.08.006〉
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http://hal.in2p3.fr/in2p3-01389477
Contributeur : Emilie Bonnardel <>
Soumis le : vendredi 28 octobre 2016 - 14:46:28
Dernière modification le : jeudi 7 février 2019 - 16:53:06

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Jublot-Leclerc S., Li X., Legras L., Lescoat M.L., Fortuna F., et al.. Microstructure of Au-ion irradiated 316L and FeNiCr austenitic stainless steels. Journal of Nuclear Materials, Elsevier, 2016, pp.436-446. 〈10.1016/j.jnucmat.2016.08.006〉. 〈in2p3-01389477〉

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