CX-022568: Corrosion Sensitivity of Stainless Steels in Pressurized Water Reactor Water Chemistry: Can KOH replace LiOH in PWRs

The University of Wisconsin (UW), in collaboration with Oregon State University (OSU), proposes to develop in-situ measurements of distributed temp…

Office of NEPA Policy and Compliance

August 31, 2020
minute read time

North Carolina State University proposes to determine if switching from lithium hydroxide (LiOH) to potassium hydroxide (KOH) to control the pH in nuclear reactors is possible without worsening the corrosion behavior of the structural alloys used in pressurized water reactor (PWR) core internal components.