Zitieren Sie bitte immer diesen URN: urn:nbn:de:kobv:b43-595748
How irradiation promotes intergranular stress corrosion crack initiation
- 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 nuclearIrradiation 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.…
Autor*innen: | 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, Srinivasan Swaminathan, M. Wang, E. West |
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Dokumenttyp: | Zeitschriftenartikel |
Veröffentlichungsform: | Verlagsliteratur |
Sprache: | Englisch |
Titel des übergeordneten Werkes (Englisch): | Progress in Material Science |
Jahr der Erstveröffentlichung: | 2024 |
Organisationseinheit der BAM: | 5 Werkstofftechnik |
5 Werkstofftechnik / 5.1 Mikrostruktur Design und Degradation | |
Veröffentlichende Institution: | Bundesanstalt für Materialforschung und -prüfung (BAM) |
Verlag: | Elsevier |
Jahrgang/Band: | 143 |
Aufsatznummer: | 101255 |
Erste Seite: | 1 |
Letzte Seite: | 15 |
DDC-Klassifikation: | Technik, Medizin, angewandte Wissenschaften / Ingenieurwissenschaften / Ingenieurwissenschaften und zugeordnete Tätigkeiten |
Freie Schlagwörter: | Austenitic alloys; Grain boundaries; Irradiation; Oxidation; Stress corrosion cracking |
Themenfelder/Aktivitätsfelder der BAM: | Material |
Material / Degradation von Werkstoffen | |
DOI: | 10.1016/j.pmatsci.2024.101255 |
URN: | urn:nbn:de:kobv:b43-595748 |
ISSN: | 0079-6425 |
Verfügbarkeit des Dokuments: | Datei für die Öffentlichkeit verfügbar ("Open Access") |
Lizenz (Deutsch): | Creative Commons - CC BY-NC-ND - Namensnennung - Nicht kommerziell - Keine Bearbeitungen 4.0 International |
Datum der Freischaltung: | 28.02.2024 |
Referierte Publikation: | Ja |
Datum der Eintragung als referierte Publikation: | 08.04.2024 |
Schriftenreihen ohne Nummerierung: | Wissenschaftliche Artikel der BAM |