Introduction to Stress Corrosion Cracking in Light Water Reactors

Presented by: Barry Gordon, P.E.
Materials corrosion degradation in light water reactors (LWRs), particularly of primary pressure boundary components, has a significant effect on plant capacity factor. In general, each problem resolution causes a sense of optimism that all corrosion degradation problems are resolved, when in fact most corrosion problems while mitigated are not eliminated, and new corrosion problems continually emerge. Stress corrosion cracking (SCC) remains the most serious of materials degradation in LWRs.

Don't face this alone - let our experts help.

After a brief introduction regarding SCC in LWRs we’ll cover:

  • SCC Parameters
  • Ductile vs. SCC Failures
  • Historic Examples of SCC
  • Stress Corrosion Cracking Modes
  • Testing for SCC Initiation and Growth
  • SCC in LWR: IGSCC in BWRs, PWSCC in PWRs and IASCC in LWRs and their Mitigation

This is your opportunity to attend a very purposefully planned webinar that is designed to help improve your understanding of SCC in LWRs. When you are armed with the basic understanding of SCC, you will be able to discuss SCC with more confidence, as well as make better-informed SCC mitigation recommendations and decisions.

Who Should Attend:

This webinar should be attended by anyone who has dealt directly or is in any way concerned with the most insidious form of localized corrosion.

Presented on: August 30th 2016

Request Recording

Faculty Spotlight

Barry Gordon, P.E., Associate
Nuclear Plant Services, Structural Integrity Associates


Barry received his Bachelors of Science and Masters of Science degrees in Materials Science and Engineering from Carnegie Mellon University. He is a Professional Engineer (P.E.) - Corrosion Engineering and has been an Associate with Structural Integrity for more than 18 years. Barry is a NACE International Fellow and NACE Corrosion Specialist and an NRC instructor for "Corrosion and Corrosion Control in LWRs.