A METHOD OF STRENGTH ASSESSMENT OF WWER REACTOR INTERNALS BY THE CRITERION OF STRESS CORROSION CRACKING IN IRRADIATED AUSTENITIC STEELS

摘要

The authors analyze experimental data on the tendency of irradiated austenitic stainless steels toundergo intergranular stress corrosion cracking when in contact with a WWER primary coolant.Based on the analysis, a physical-mechanical model of cracking in these steels is put forward. Aprocedure for the assessment of service life of pressure vessel internals by the corrosion crackingcriterion has been elaborated; it allows calculations to be performed for a time-varying stressstrainstate and damaging dose.