International Round-Robin on Stress Corrosion Crack Initiation of Alloy 600 Material in Pressurized Water Reactor Primary Water

P.J. Meadows, P.L. Andresen, M.B. Toloczko, W.-J. Kuang, S. Ritter, M. Burman, L. Zhang, M. Ernestova, Aki Toivonen, F. Perosanz-Lopez, J.W. Stairmand, K.J. Mottershead (Corresponding Author)

Research output: Contribution to journalArticleScientificpeer-review

Abstract

The International Cooperative Group on Environmentally Assisted Cracking of Water Reactor Materials coordinated an international “Round-Robin” collaboration of 10 laboratories on stress corrosion crack (SCC) initiation in three heats of cold-worked Alloy 600 in high-temperature water. The various laboratories were able to produce good quality experimental crack initiation data, and the Round-Robin exercise highlighted the benefits in generating a significant body of data when assessing the susceptibility of a material to SCC. The compilation of data from multiple laboratories using common test techniques greatly assists the understanding of the material variability and gives confidence in the reliability of the results.
Original languageEnglish
Pages (from-to)719-733
JournalCorrosion
Volume76
Issue number8
DOIs
Publication statusPublished - Aug 2020
MoE publication typeA1 Journal article-refereed

Keywords

  • alloy
  • nickel
  • stress corrosion testing

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    Meadows, P. J., Andresen, P. L., Toloczko, M. B., Kuang, W-J., Ritter, S., Burman, M., Zhang, L., Ernestova, M., Toivonen, A., Perosanz-Lopez, F., Stairmand, J. W., & Mottershead, K. J. (2020). International Round-Robin on Stress Corrosion Crack Initiation of Alloy 600 Material in Pressurized Water Reactor Primary Water. Corrosion, 76(8), 719-733. https://doi.org/10.5006/3532