Modeling solute-vacancy trapping at oversized solutes and its effect on radiation-induced segregation in Fe–Cr–Ni alloys

Effects of oversized solutes on radiation-induced segregation in austenitic stainless steels

“…Since the MIK-T model was shown in Ref. [35] to be relatively insensitive to both variables, decreasing the interaction volumes would have virtually no effect on segregation, so decreasing the trapping or recombination radii is unlikely to be the cause for the loss of effect from oversized solutes on RIS.…”

“…The MIK-T model, described fully in Ref. [35], includes the effects of oversized solutes on RIS behavior. A comparison between experiment and model results provides an indication of whether the vacancy trapping mechanism can adequately describe the observed behavior.…”

“…[35], ab initio calculations had determined that the solute-vacancy binding energy for Zr, at 1.08 eV, is larger than for Hf, at 0.71 eV, meaning that Zr should be more effective in suppressing RIS than Hf. Thus, the MIK-T model predicts a larger reduction in RIS for Zr as compared to Hf.…”

The role of niobium carbide in radiation induced segregation behaviour of type 347 austenitic stainless steel

“…Radiation-induced segregation (RIS) is considered to be part of a complex process that increases the susceptibility of in-core austenitic stainless steel (SS) components to irradiation assisted stress corrosion cracking (IASCC) in light water reactors (LWR) [1][2][3][4]. The RIS is a non-equilibrium segregation of alloying elements resulting from generation of point defects far in excess of equilibrium concentration at a given temperature [1] and it leads to enrichment of nickel, silicon, and phosphorus in addition to depletion of chromium at grain boundaries [5].…”

“…(1) and fitted using Eq. (2) and (b) variation of DL-EPR values with dpa along with a fitted curve using equation(4).…”