Stress-damage dose curve (SDDC) is introduced on the basis of the analysis of experimental data on susceptibility to intergranular stress corrosion cracking (IGSCC) of irradiated stainless steels (SS). Approaches to determination of the SDDC parameters are considered. Based on SDDC calculative procedure for estimation of reactor vessel internals (RVI) lifetime by criterion of initiation crack due to IGSCC is proposed.

Volume Subject Area:
Materials and Fabrication
Topics:
Stress corrosion cracking, Damage, Fracture (Materials), Reactor vessels, Stainless steel, Stress
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Copyright © 2009
 by ASME
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