How irradiation promotes intergranular stress corrosion crack initiation

G. S. Was; C. B. Bahn; J. Busby; B. Cui; D. Farkas; M. Gussev; M. Rigen He; J. Hesterberg; Z. Jiao; D. Johnson; W. Kuang; M. McMurtrey; I. Robertson; A. Sinjlawi; M. Song; K. Stephenson; K. Sun; S. Swaminathan; M. Wang; E. West

doi:10.1016/j.pmatsci.2024.101255

How irradiation promotes intergranular stress corrosion crack initiation

G. S. Was, C. B. Bahn, J. Busby, B. Cui, D. Farkas, M. Gussev, M. Rigen He, J. Hesterberg, Z. Jiao, D. Johnson, W. Kuang, M. McMurtrey, I. Robertson, A. Sinjlawi, M. Song, K. Stephenson, K. Sun, S. Swaminathan, M. Wang, E. West

Research output: Contribution to journal › Review article › peer-review

Abstract

Irradiation assisted stress corrosion cracking (IASCC) is a form of intergranular stress corrosion cracking that occurs in irradiated austenitic alloys. It requires an irradiated microstructure along with high temperature water and stress. The process is ubiquitous in that it occurs in a wide range of austenitic alloys and water chemistries, but only when the alloy is irradiated. Despite evidence of this degradation mode that dates back to the 1960s, the mechanism by which it occurs has remained elusive. Here, using high resolution electron backscattering detection to analyze local stress-strain states, high resolution transmission electron microscopy to identify grain boundary phases at crack tips, and decoupling the roles of stress and grain boundary oxidation, we are able to unfold the complexities of the phenomenon to reveal the mechanism by which IASCC occurs. The significance of the findings impacts the mechanical integrity of core components of both current and advanced nuclear reactor designs worldwide.

Original language	English
Article number	101255
Journal	Progress in Materials Science
Volume	143
Early online date	Feb 16 2024
DOIs	https://doi.org/10.1016/j.pmatsci.2024.101255
State	E-pub ahead of print - Feb 16 2024

Keywords

Austenitic alloys
Dislocation channels
Grain boundaries
Irradiation
Localized deformation
Oxidation
Stress corrosion cracking

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10.1016/j.pmatsci.2024.101255

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Was, G. S., Bahn, C. B., Busby, J., Cui, B., Farkas, D., Gussev, M., Rigen He, M., Hesterberg, J., Jiao, Z., Johnson, D., Kuang, W., McMurtrey, M., Robertson, I., Sinjlawi, A., Song, M., Stephenson, K., Sun, K., Swaminathan, S., Wang, M., & West, E. (2024). How irradiation promotes intergranular stress corrosion crack initiation. Progress in Materials Science, 143, Article 101255. Advance online publication. https://doi.org/10.1016/j.pmatsci.2024.101255

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title = "How irradiation promotes intergranular stress corrosion crack initiation",

abstract = "Irradiation assisted stress corrosion cracking (IASCC) is a form of intergranular stress corrosion cracking that occurs in irradiated austenitic alloys. It requires an irradiated microstructure along with high temperature water and stress. The process is ubiquitous in that it occurs in a wide range of austenitic alloys and water chemistries, but only when the alloy is irradiated. Despite evidence of this degradation mode that dates back to the 1960s, the mechanism by which it occurs has remained elusive. Here, using high resolution electron backscattering detection to analyze local stress-strain states, high resolution transmission electron microscopy to identify grain boundary phases at crack tips, and decoupling the roles of stress and grain boundary oxidation, we are able to unfold the complexities of the phenomenon to reveal the mechanism by which IASCC occurs. The significance of the findings impacts the mechanical integrity of core components of both current and advanced nuclear reactor designs worldwide.",

keywords = "Austenitic alloys, Dislocation channels, Grain boundaries, Irradiation, Localized deformation, Oxidation, Stress corrosion cracking",

author = "Was, {G. S.} and Bahn, {C. B.} and J. Busby and B. Cui and D. Farkas and M. Gussev and {Rigen He}, M. and J. Hesterberg and Z. Jiao and D. Johnson and W. Kuang and M. McMurtrey and I. Robertson and A. Sinjlawi and M. Song and K. Stephenson and K. Sun and S. Swaminathan and M. Wang and E. West",

note = "Funding Information: This work was supported by the Office of Basic Energy Sciences, U.S. Department of Energy awards DE-FG02-08ER46525 and DE-FG07-05ID14703; Nuclear Energy University Program, Office of Nuclear Energy, U.S. Department of Energy award DE-AC07-05ID14517; Light Water Reactor Sustainability Program, Office of Nuclear Energy, U.S. Department of Energy awards 400079632 and 4000185584; U.S. Department of Energy awards F031891, 4000136101 and 4000129492; Electric Power Research Institute awards EP-P20783/C10134, EP-P39425/C17515, 10002154, 10002164, 10003608, 10003872, 10002970; Michigan Ion Beam Laboratory; Michigan Center for Materials Characterization; and the many helpful discussions with Peter Scott, Peter Andresen and Stephen Bruemmer. Publisher Copyright: {\textcopyright} 2024 The Author(s)",

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doi = "10.1016/j.pmatsci.2024.101255",

language = "English",

volume = "143",

journal = "Progress in Materials Science",

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Was, GS, Bahn, CB, Busby, J, Cui, B, Farkas, D, Gussev, M, Rigen He, M, Hesterberg, J, Jiao, Z, Johnson, D, Kuang, W, McMurtrey, M, Robertson, I, Sinjlawi, A, Song, M, Stephenson, K, Sun, K, Swaminathan, S, Wang, M & West, E 2024, 'How irradiation promotes intergranular stress corrosion crack initiation', Progress in Materials Science, vol. 143, 101255. https://doi.org/10.1016/j.pmatsci.2024.101255

TY - JOUR

T1 - How irradiation promotes intergranular stress corrosion crack initiation

AU - Was, G. S.

AU - Bahn, C. B.

AU - Busby, J.

AU - Cui, B.

AU - Farkas, D.

AU - Gussev, M.

AU - Rigen He, M.

AU - Hesterberg, J.

AU - Jiao, Z.

AU - Johnson, D.

AU - Kuang, W.

AU - McMurtrey, M.

AU - Robertson, I.

AU - Sinjlawi, A.

AU - Song, M.

AU - Stephenson, K.

AU - Sun, K.

AU - Swaminathan, S.

AU - Wang, M.

AU - West, E.

N1 - Funding Information: This work was supported by the Office of Basic Energy Sciences, U.S. Department of Energy awards DE-FG02-08ER46525 and DE-FG07-05ID14703; Nuclear Energy University Program, Office of Nuclear Energy, U.S. Department of Energy award DE-AC07-05ID14517; Light Water Reactor Sustainability Program, Office of Nuclear Energy, U.S. Department of Energy awards 400079632 and 4000185584; U.S. Department of Energy awards F031891, 4000136101 and 4000129492; Electric Power Research Institute awards EP-P20783/C10134, EP-P39425/C17515, 10002154, 10002164, 10003608, 10003872, 10002970; Michigan Ion Beam Laboratory; Michigan Center for Materials Characterization; and the many helpful discussions with Peter Scott, Peter Andresen and Stephen Bruemmer. Publisher Copyright: © 2024 The Author(s)

PY - 2024/2/16

Y1 - 2024/2/16

N2 - Irradiation assisted stress corrosion cracking (IASCC) is a form of intergranular stress corrosion cracking that occurs in irradiated austenitic alloys. It requires an irradiated microstructure along with high temperature water and stress. The process is ubiquitous in that it occurs in a wide range of austenitic alloys and water chemistries, but only when the alloy is irradiated. Despite evidence of this degradation mode that dates back to the 1960s, the mechanism by which it occurs has remained elusive. Here, using high resolution electron backscattering detection to analyze local stress-strain states, high resolution transmission electron microscopy to identify grain boundary phases at crack tips, and decoupling the roles of stress and grain boundary oxidation, we are able to unfold the complexities of the phenomenon to reveal the mechanism by which IASCC occurs. The significance of the findings impacts the mechanical integrity of core components of both current and advanced nuclear reactor designs worldwide.

AB - Irradiation assisted stress corrosion cracking (IASCC) is a form of intergranular stress corrosion cracking that occurs in irradiated austenitic alloys. It requires an irradiated microstructure along with high temperature water and stress. The process is ubiquitous in that it occurs in a wide range of austenitic alloys and water chemistries, but only when the alloy is irradiated. Despite evidence of this degradation mode that dates back to the 1960s, the mechanism by which it occurs has remained elusive. Here, using high resolution electron backscattering detection to analyze local stress-strain states, high resolution transmission electron microscopy to identify grain boundary phases at crack tips, and decoupling the roles of stress and grain boundary oxidation, we are able to unfold the complexities of the phenomenon to reveal the mechanism by which IASCC occurs. The significance of the findings impacts the mechanical integrity of core components of both current and advanced nuclear reactor designs worldwide.

KW - Austenitic alloys

KW - Dislocation channels

KW - Grain boundaries

KW - Irradiation

KW - Localized deformation

KW - Oxidation

KW - Stress corrosion cracking

UR - http://www.scopus.com/inward/record.url?scp=85186402991&partnerID=8YFLogxK

U2 - 10.1016/j.pmatsci.2024.101255

DO - 10.1016/j.pmatsci.2024.101255

M3 - Review article

AN - SCOPUS:85186402991

SN - 0079-6425

VL - 143

JO - Progress in Materials Science

JF - Progress in Materials Science

M1 - 101255

ER -

How irradiation promotes intergranular stress corrosion crack initiation

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