Long-term initiation time for stress -corrosion cracking of alloy 600 with implications in stainless steel: Review and analysis for nuclear application
This paper provides a summary and analysis on the initiation of stress -corrosion cracking (SCC) of Alloy 600 (and related alloys) and stainless steels in nuclear reactor environments near 300 °C. Two processes seem to be comparable between traditional slip dissolution/oxidation mechanisms and aging...
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| Veröffentlicht in: | Progress in nuclear energy (New series) 2021-07, Vol.137, p.103760, Article 103760 |
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| container_title | Progress in nuclear energy (New series) |
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| creator | Ahn, Tae M. |
| description | This paper provides a summary and analysis on the initiation of stress -corrosion cracking (SCC) of Alloy 600 (and related alloys) and stainless steels in nuclear reactor environments near 300 °C. Two processes seem to be comparable between traditional slip dissolution/oxidation mechanisms and aging-related crystalline ordering. This paper evaluates various supporting topics, including SCC initiation time, activation energy, stress/strain rate/plastic deformation, electrode potential drop, rate-limiting step, long-term threshold values, and data uncertainties. The understanding of Alloy 600 SCC is extended to stainless steels. SCC mechanisms of nickel-based alloys and stainless steels at lower temperatures are different from nickel-based alloys at higher temperatures. Finally, this paper describes how this work would be potentially considered in the nuclear industry. |
| doi_str_mv | 10.1016/j.pnucene.2021.103760 |
| format | Article |
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Two processes seem to be comparable between traditional slip dissolution/oxidation mechanisms and aging-related crystalline ordering. This paper evaluates various supporting topics, including SCC initiation time, activation energy, stress/strain rate/plastic deformation, electrode potential drop, rate-limiting step, long-term threshold values, and data uncertainties. The understanding of Alloy 600 SCC is extended to stainless steels. SCC mechanisms of nickel-based alloys and stainless steels at lower temperatures are different from nickel-based alloys at higher temperatures. Finally, this paper describes how this work would be potentially considered in the nuclear industry.</description><identifier>ISSN: 0149-1970</identifier><identifier>EISSN: 1878-4224</identifier><identifier>DOI: 10.1016/j.pnucene.2021.103760</identifier><language>eng</language><publisher>Oxford: Elsevier Ltd</publisher><subject>Alloy 600 ; Alloys ; Crack initiation ; Crystalline ordering ; Initiation ; Microstructure ; Nickel base alloys ; Nuclear reactors ; Oxidation ; Plastic deformation ; Review and analysis ; Stainless steel ; Stainless steels ; Strain rate ; Stress corrosion cracking ; Studies ; Superalloys ; Voltage drop</subject><ispartof>Progress in nuclear energy (New series), 2021-07, Vol.137, p.103760, Article 103760</ispartof><rights>2021 Elsevier Ltd</rights><rights>Copyright Elsevier BV Jul 2021</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c337t-5a78108f98bb48ddea8bf5b1e27e86768a5d6c9488d8a20c32c82e2a71c7bc453</citedby><cites>FETCH-LOGICAL-c337t-5a78108f98bb48ddea8bf5b1e27e86768a5d6c9488d8a20c32c82e2a71c7bc453</cites><orcidid>0000-0002-5354-1420</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S014919702100127X$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,776,780,3537,27901,27902,65306</link.rule.ids></links><search><creatorcontrib>Ahn, Tae M.</creatorcontrib><title>Long-term initiation time for stress -corrosion cracking of alloy 600 with implications in stainless steel: Review and analysis for nuclear application</title><title>Progress in nuclear energy (New series)</title><description>This paper provides a summary and analysis on the initiation of stress -corrosion cracking (SCC) of Alloy 600 (and related alloys) and stainless steels in nuclear reactor environments near 300 °C. 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| identifier | ISSN: 0149-1970 |
| ispartof | Progress in nuclear energy (New series), 2021-07, Vol.137, p.103760, Article 103760 |
| issn | 0149-1970 1878-4224 |
| language | eng |
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| source | Elsevier ScienceDirect Journals |
| subjects | Alloy 600 Alloys Crack initiation Crystalline ordering Initiation Microstructure Nickel base alloys Nuclear reactors Oxidation Plastic deformation Review and analysis Stainless steel Stainless steels Strain rate Stress corrosion cracking Studies Superalloys Voltage drop |
| title | Long-term initiation time for stress -corrosion cracking of alloy 600 with implications in stainless steel: Review and analysis for nuclear application |
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