October 27, 2022
Conference Paper

Intergranular Oxidation of Unstressed Alloy 600 SA and Alloy 600TT in PWR Primary Water

Abstract

Unstressed coupons of Alloy 600 SA (solution-annealed) and Alloy 600TT were exposed to simulated pressurized water reactor (PWR) primary water at 360oC. The depth of intergranular oxide penetration, as well as the microstructure and microchemistry associated with intergranular (IG) oxidation of selected samples, were characterized by SEM, serial FIB sectioning, TEM and APT. There is no clear trend to indicate that IG oxidation depths in unstressed coupons are different between Alloy 600 SA and TT. At the same time, all SA+TT materials examined evidenced significant interaction between oxidation and Cr-rich GB precipitates. In addition, the spatial extent of GB compositional changes ahead of the oxidation front (e.g. Cr depletion and Ni enrichment) appears different for Alloy 600 SA vs. SA+TT. In SA heats exposed for only 1000 h (42 days), the composition of some GBs changes over distances of 500–1000 nm. SA+TT materials appear not to develop such long-range GB compositional changes (10s nm alteration distances only).

Published: October 27, 2022

Citation

Schreiber D.K., K. Kruska, M.J. Olszta, and P. Chou. 2022. Intergranular Oxidation of Unstressed Alloy 600 SA and Alloy 600TT in PWR Primary Water. In Proceedings of the 20th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, July 17-21, 2022, Snowmass, CO, ED22-17279-SG. Pittsburgh, Pennsylvania:Association for Materials Protection and Performance. PNNL-SA-178120.