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Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part I: Evolution of the microstructure |
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| Authors: | C Pokor Y Brechet J.-P Massoud A Barbu |
| Affiliation: | a CEA/DEN/SRMA, CEA Saclay, 91191 Gif sur Yvette cedex, France b EDF/GDL/SECH, BP23-37420 Avoine cedex, France c LTPCM, BP75, Domaine Universitaire de Grenoble, 38402 Saint Martin d’Hères cedex, France d EDF R&D, MMC, Site des Renardières, 77818 Moret sur Loing cedex, France e CEA/DEN/SRMP, CEA Saclay, 91191 Gif sur Yvette cedex, France |
| Abstract: | Irradiation damage in three austenitic stainless steels, SA 304L, CW 316 and CW Ti-modified 316, is investigated both experimentally and theoretically. The density and size of Frank loops after irradiation at 320 and 375 °C in experimental EBR II, BOR-60 and OSIRIS reactors for doses up to 40 dpa are characterized by TEM. The evolution of the initial dislocation network under irradiation is evaluated. A cluster dynamics model is proposed to account quantitatively for the experimental findings. |
| Keywords: | D0400 N0100 R0200 S0500 T0100 |
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