IRRADIATION-ASSISTED STRESS CORROSION CRACK GROWTH RATES OF AUSTENITIC STAINLESS STEELS IN LIGHT WATER REACTOR ENVIRONMENTS

摘要

Irradiation-assisted stress corrosion cracking (IASCC) models from a multi-year international data collection, data review and modeling project are presented. The project collected more than 800 IASCC crack growth rate (CGR) data points from six laboratories worldwide. An international Expert Panel reviewed and ranked the data, helped to define data sets for modeling, and reviewed the model development and project reports. The review and ranking procedure and the custom modeling process used to address the large variations in measured CGR are described. The better-ranked data were used to calibrate empirical models for IASCC CGR in boiling water reactor (BWR) normal water chemistry (NWC) and hydrogen water chemistry (HWC) environments and in pressurized water reactor (PWR) primary water environments. The models are compared in this paper with laboratory data used for calibration and with other data not used for calibration.