Stress Corrosion Cracking in Nuclear Plant

Stress corrosion cracking (SCC) is one of the significant ageing degradations for major components of pressurised water reactors (PWRs), boiling water reactors (BWRs) and advanced gas-cooled reactors (AGRs) and is an important technical issue for the nuclear industry.

SCC is the term given to crack initiation and sub-critical crack growth of susceptible alloys under the influence of tensile stress and a ‘corrosive’ environment. SCC is a complex phenomenon driven by the synergistic interaction of mechanical, electrochemical and metallurgical factors and large efforts have been dedicated worldwide to understand, reduce or eliminate it.

This seminar, Stress Corrosion Cracking in Nuclear Plant, aims to provide an overview of the current status of SCC management in the nuclear industry. The presentations will be delivered by industry experts with many years’ experience in the field and range from theoretical and laboratory scale research to application in real plants from around the world.