Experimental validation of intergranular stress corrosion cracking predictive models

<p>Intergranular Stress Corrosion Cracking (IGSCC) has been one of the most important challenges to nuclear power plant operation worldwide. The degradation of alloy 600 (Ni-based alloy) and its susceptibility to Stress Corrosion Cracking (SCC) when exposed to primary water environment in pres...

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Bibliographic Details
Main Author: Saravanan, N
Other Authors: Lozano-Perez, S
Format: Thesis
Language:English
Published: 2022
Subjects:
Description
Summary:<p>Intergranular Stress Corrosion Cracking (IGSCC) has been one of the most important challenges to nuclear power plant operation worldwide. The degradation of alloy 600 (Ni-based alloy) and its susceptibility to Stress Corrosion Cracking (SCC) when exposed to primary water environment in pressurized water reactors (PWRs) has been a topic of interest for many decades among the SCC community. However, the understanding or prediction of SCC mechanisms remains questionable. To address this, an IGSCC predictive model called ‘Local Model’ has been developed in the framework of EDF’s CSI project. The main focus of this research is to investigate IGSCC in alloy 600 and to experimentally validate a predictive model. Firstly, it is important to know whether stress corrosion cracking occurs in these materials, in the way presented in the existing experiments and models in the literature. These have shown a very large scattering for the needed for the crack initiation and crack propagation, indicating significant model uncertainties.</p> <p>In this thesis, an experimental and modelling program has been developed for investigating SCC in alloy 600 for conditions simulating PWR conditions under constant load. The goal of the experiments was to find a reliable and quantitative determination of crack initiation and crack propagation for these conditions. For the modelling aspect, the aim was to determine the critical parameters of SCC by considering the phenomena in the local scale of grain boundaries and crack tips. The model requirements include the ability to predict the crack initiation and to model crack growth rate as a function of macroscopic and measurable parameters. This has been validated by experiment to ensure that the assumptions of the model are realistic enough to make sure of reliability for reactor safety applications. By doing this, the model allows for a better understanding of the underlying mechanisms of SCC. As such, it focuses on the phenomenological approach rather than the empirical approaches in other models.</p>