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In order to predict InterGranular Stress Corrosion Cracking (IGSCC) ofpost-irradiated austenitic stainless steel in Light Water Reactor (LWR)environment, reliable predictions of intergranular stresses are required.Finite elements simulations have been performed on realistic polycrystallineaggregate with a recently proposed physically-based crystal plasticityconstitutive equations validated for neutron-irradiated austenitic stainlesssteel. Intergranular normal stress probability density functions are found withrespect to plastic strain and irradiation level, for uniaxial loadingconditions. In addition, plastic slip activity jumps at grain boundaries arealso presented. Intergranular normal stress distributions describe, from astatistical point of view, the potential increase of intergranular stress withrespect to the macroscopic stress due to grain-grain interactions. Thedistributions are shown to be well described by a master curve once rescaled bythe macroscopic stress, in the range of irradiation level and strain consideredin this study. The upper tail of this master curve is shown to be insensitiveto free surface effect, which is relevant for IGSCC

Intergranular stress distributions in polycrystalline aggregates of irradiated stainless steel