Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part I: Evolution of the microstructure

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 ar...

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Veröffentlicht in:	Journal of nuclear materials 2004-03, Vol.326 (1), p.19-29
Hauptverfasser:	Pokor, C, Brechet, Y, Dubuisson, P, Massoud, J.-P, Barbu, A
Format:	Artikel
Sprache:	eng
Schlagworte:	Applied sciences Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Installations for energy generation and conversion: thermal and electrical energy
Online-Zugang:	Volltext
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Zusammenfassung:	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.
ISSN:	0022-3115 1873-4820
DOI:	10.1016/j.jnucmat.2003.11.007