Atomic scale investigation of radiation-induced segregation in austenitic stainless steels

Atomistic Analysis Of Radiation-Induced Segregation In Ion-Irradiated Stainless Steel 316

“…Although the quantitative concentration of the APT specimen is closely related to the binning size of atoms in the selected region of the atomic maps, the distinct enrichment of Si was clearly evident. The results of Etienne on cold-worked SS316, irradiated with Fe 5+ ions at 350 • C to 10 dpa, showed similar defect types: torus-shaped and rounded Ni-Si clusters, and segregation at dislocations and grain boundaries [17]. The rounded clusters showed the highest enrichment of Si, similar to our present results.…”

“…Thus, further analysis technique is needed to reveal the nature of the cluster in detail. Table 2 summarizes the compositions of the irradiation defects of the present work and previously reported APT results of SS irradiated under various conditions [17,18]. In our present study, Si and Ni are highly enriched, and the dislocation loop and the rounded cluster show a very high peak concentration of Si.…”

“…Atom probe needles were prepared using a Helios Nanolab 650 dual beam SEM/FIB instrument from FEI. The detailed procedure of the preparation of APT is described elsewhere [17]. Fig.…”

“…The various types of radiation-induced defects were identified and the compositional characteristics were quantitatively provided with a wide view point. The measured concentrations were compared with values of the literature [17,18]. To estimate the RIS behavior, a basic modeling was established and compared with the literature.…”

Radiation-induced segregation and corrosion behavior on Σ3 coincidence site lattice and random grain boundaries in proton-irradiated type-316L austenitic stainless steel

“…Solute redistribution in concentrated alloys under irradiation results from the preferential interaction between the solute atoms and excess point defects migrating toward sinks, such as dislocations, surfaces and grain boundaries [1][2][3]. In austenitic stainless steels, which are used as core materials for the boiling water reactor (BWR) and pressurized water reactor (PWR), radiation-induced segregation (RIS) near the grain boundaries degrades their mechanical and chemical properties significantly [4][5][6][7].…”