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Effect Of Water Chemistry On Crack Growth Rates In Neutron Irradiated X-750 And XM-19

Product Number: ED22-17287-SG

Author: John Jackson, Drew Johnson, Robert G. Carter, Michael Heighes, Peter L. Andresen

Publication Date: 2022

$20.00

As the current reactor fleet continues to age, with many reactors wanting to extend operational licenses beyond their initial 40 lifetime, it is becoming increasingly important to understand how structural materials in these reactor environments will degrade over time. A critical material degradation mode which can limit the lifetime of reactor components is irradiation assisted stress corrosion cracking (IASCC). As the name implies, a material must be subjected to both a corrosive environment as well as mechanical stresses while the original material microstructure has been affected by irradiation.

Products tagged with 'electrochemical potential'

Effect Of Water Chemistry On Crack Growth Rates In Neutron Irradiated X-750 And XM-19

Association for Materials Protection and Performance