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

doi:10.5006/3532

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 for this work

Jacobs, UK
General Electric
Pacific Northwest National Laboratory (PNNL)
University of Michigan–Ann Arbor
Paul Scherrer Institute (PSI)
Studsvik AB
Shanghai Jiao Tong University
ÚJV Řež a.s.
Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT)

Research output: Contribution to journal › Article › Scientific › peer-review

8 Citations (Scopus)

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 language	English
Pages (from-to)	719-733
Journal	Corrosion
Volume	76
Issue number	8
DOIs	https://doi.org/10.5006/3532
Publication status	Published - Aug 2020
MoE publication type	A1 Journal article-refereed

Funding

The financial support by the following organizations is acknowledged: Electric Power Research Institute (EPRI), University of Michigan, Swiss Federal Nuclear Safety Inspectorate (ENSI), Swedish Radiation Safety Authority, Ringhals AB, Forsmarks Kraftgrupp AB, Oskarshamns Kraft AB, Studsvik Nuclear AB, The National Natural Science Foundation of China, UJV, Project THELMA of the Finnish national nuclear power plant safety program SAFIR2018, CEIMAT, and the U.S. Department of Energy LWRS Program.

Keywords

alloy
nickel
stress corrosion testing
stress corrosion

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10.5006/3532

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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

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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.",

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AU - Ritter, S.

AU - Burman, M.

AU - Zhang, L.

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AU - Toivonen, Aki

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

Abstract

Funding

Keywords

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