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Role of Grain Boundary Oxidation in Crack Initiation of Neutron-irradiated Stainless Steel

Product Number: ED22-17333-SG

Author: Srinivasan Swaminathan, Donghai Du, Gary S. Was

Publication Date: 2022

$20.00

Irradiation assisted stress corrosion cracking (IASCC) continues to be a major concern for the
structural integrity of core internals in both pressurized water reactors (PWRs) and boiling water
reactor (BWRs). While factors such as stress, an irradiated microstructure and a high temperature
water environment are required for IASCC, a better understanding of the underlying mechanism
has become a subject of intense long-term research. In the last two decades, much progress has
been made in understanding IASCC susceptibility, though a clear cause-and-effect has yet to be
established on the mechanism of intergranular cracking in highly neutron irradiated stainless steels
in the PWR environment.

Products tagged with 'grain boundary oxidation'

Role of Grain Boundary Oxidation in Crack Initiation of Neutron-irradiated Stainless Steel

Association for Materials Protection and Performance