As from long-term operating experience the high purity primary water cycle of light water nuclear reactors may exhibit excursions from the recommended water chemistry leading to potentially favorite conditions for stress corrosion cracking (SCC) which may be initiated and its propagation controlled by local pitting and crevice corrosion.

S. Octopus

Publication type:Research Problem

Published:December 2, 2022

Language:English

Licence:

CC BY 4.0

DOI:

https://handle.test.datacite.org/10.82259/78sv-x202

Peer Reviews (This Version): (0)

Red flags:

(0)

Actions

Download:

Sections

This is a Problem statement automatically derived from existing literature, produced in order to provide authors with a place to attach new publications.

Publications above this in the hierarchy

The literature of the corrosion of metals used in high-and low-temperature water-cooled reactors is reviewed and technological and scientific advances in this field are assessed.

Funders

No sources of funding have been specified for this Research Problem.

Conflict of interest

This Research Problem does not have any specified conflicts of interest.