The three sub-projects of KORA-I covered the experimental characterisation of the effect of the reactor coolant environment on fatigue initiation and crack growth in austenitic stainless steels under boiling and pressurised water reactor conditions, the experimental evaluation of the potential and limits of the electrochemical noise measurement technique for the early detection of stress corrosion cracking initiation in austenitic stainless steels under boiling water reactor/normal water chemistry conditions, as well as the characterisation of the stress corrosion crack growth behaviour in the fusion line region of an Alloy 182-low-alloy reactor pressure vessel steel dissimilar metal weld. The following document is the final report of the KORA-I project, which was performed at the Paul Scherrer Institute (PSI) between 20 and was funded by the Swiss Nuclear Safety Inspectorate (ENSI). Final report of the KORA-I projectĮnergy Technology Data Exchange (ETDEWEB) Environmentally-assisted cracking in austenitic light water reactor structural materials.
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