Irradiation assisted stress corrosion cracking (IASCC) is a phenomenon caused by neutron irradiation of austenitic stainless steels (SSs), and it is required to evaluate the crack growth rates (CGRs) of IASCC for boiling water reactor (BWR) components to assure their integrity. However, the prediction of CGR has an uncertainty for the *K* region without any experimental data. In order to set the basis of predictions for these *K* regions, calculated results by a predictive mechanistic model are valuable.

The Hashimoto-Koshiishi model is the predictive mechanistic model for CGRs based on the slip dissolution/oxidation mechanism of stress corrosion cracking. The simplified formula of the Hashimoto-Koshiishi model was developed for the calculation of CGRs of irradiated Type 316L stainless steels (SSs). This formula well reproduces the Hashimoto-Koshiishi model calculations of Type 316L SSs. However, various types of SSs are used in core internals of BWR. It is desirable to evaluate the applicability of the developed formula to different types of SSs other from Type 316L SSs.

This study evaluated the applicability of the developed formula to various types of stainless steels by analyzing the experimental CGRs data. The developed formula was evaluated to be applicable for Type 304L SSs and 316NG SSs as well as Type 316L SSs. On the other hand, the applicability of the formula to irradiated Type 304 SSs was insufficient because the mechanical property and the Cr concentration at grain boundaries of Type SSs were different from Type 316L SSs.


Applicability of Formula of the Irradiation Assisted Stress Corrosion Cracking Rates for Neutron-Irradiated Type 316l Stainless Steels to Various Types of Stainless Steels Under Boiling Water Reactor Condition

Division / Sponsors: 
Pressure Vessels & Piping (PVP)


Paper Proceedings: https://asmedigitalcollection.asme.org/PVP/PVP2020/volume/83815

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