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A physicomechanical model for occurrence of fractures of austenitic steels upon intergranular stress corrosion cracking (IGSCC) is proposed on the basis of an analysis of experimental data on the suscep tibility of irradiated austenitic steels to IGSCC during contact with the coolant of the primary circuit of a water moderated water cooled power reactor (VVER). A durability evaluation method for units of vessel internals by the criterion of the initialization of IGSCC is developed that allows for calculations under a time varying stress strain state of the unit and a damaging radiation dose.