TY - JOUR
T1 - Irradiation damage in 304 and 316 stainless steels
T2 - experimental investigation and modeling. Part I: Evolution of the microstructure
AU - Pokor, C.
AU - Brechet, Y.
AU - Dubuisson, P.
AU - Massoud, J. P.
AU - Barbu, A.
PY - 2004/3/1
Y1 - 2004/3/1
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=1242332971&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2003.11.007
DO - 10.1016/j.jnucmat.2003.11.007
M3 - Article
AN - SCOPUS:1242332971
VL - 326
SP - 19
EP - 29
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
SN - 0022-3115
IS - 1
ER -