Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels and Alloy 690 from Halden Phase-II Irradiations

摘要

The work is an ongoing effort at Argonne National Laboratory on the mechanistic study of irradiation-assisted stress corrosion cracking (IASCC) in the core internals of light water reactors. Phase II in this effort focused on determining the influence of grain boundary engineering (GBE), alloying elements, and neutron dose on the IASCC susceptibility of austenitic stainless steels (SSs) and Alloy 690. Flat dog-bone specimens irradiated in the Halden boiling heavy water reactor to neutron doses of approx. 2 displacements per atom (dpa) were subjected to slow strain rate tensile (SSRT) tests in high dissolved oxygen water at 289 degrees C. The areas of the fracture surfaces with brittle fracture morphology (intergranular and transgranular cleavage cracking) were measured with a scanning electron microscope.