Abstract
Modeling of radiation-induced segregation at grain boundaries in Fe–Cr–Ni alloys was carried out for wide ranges of temperatures, point defects generation rates and doses taking into account both the vacancy and interstitial mechanisms of the alloy components diffusion. To explain available data on deterioration of both the radiation-induced segregation and void swelling in austenitic stainless steels doped with oversized substitutional atoms (Ti, Nb, Ta, Zr or Hf) a physical model is proposed. Results of calculating the time of desegregation of components in Fe–Cr–Ni alloys near grain boundary during isothermal post-irradiation annealing are presented.
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