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Intergranular Oxidation and Oxygen Transport in Ni-20Cr During Exposure to Model Dry and Wet Oxidation Environments

Product Number: ED22-17329-SG

Author: Martin Weiser, Daniel K. Schreiber, Karen Kruska, Mark H. Engelhard, Matthew J. Olszta

Publication Date: 2022

$20.00

The austenitic Ni-base Alloy 600 has been extensively used as structural material in primary water reactors (PWR). Despite good resistance against general corrosion in water-cooled nuclear power reactors, the material has been susceptible to stress corrosion cracking (SCC). These observations have led to ongoing discussions of the underlying embrittlement mechanism(s). Internal oxidation of the grain boundary (GB) at typical operating temperatures is one such mechanism, although debate continues on the exact mechanisms at play.

Products tagged with 'internal oxidation'

Intergranular Oxidation and Oxygen Transport in Ni-20Cr During Exposure to Model Dry and Wet Oxidation Environments

Association for Materials Protection and Performance