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Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions
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| Zeitschriftentitel: | AECL Nuclear Review |
|---|---|
| Personen und Körperschaften: | |
| In: | AECL Nuclear Review, 1, 2012, 1, S. 13-20 |
| Format: | E-Article |
| Sprache: | Englisch |
| veröffentlicht: |
Canadian Nuclear Laboratories Limited
|
| Schlagwörter: |
| author_facet |
Lu, Y. Lu, Y. |
|---|---|
| author |
Lu, Y. |
| spellingShingle |
Lu, Y. AECL Nuclear Review Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions General Medicine |
| author_sort |
lu, y. |
| spelling |
Lu, Y. 1929-8056 1929-6371 Canadian Nuclear Laboratories Limited General Medicine http://dx.doi.org/10.12943/anr.2012.00003 <jats:p>The localized corrosion resistance of nuclear-grade Alloy 800, which is one of the preferred steam generator (SG) heat exchange tube materials of CANDU and PWR reactors, was studied under simulated SG secondary side crevice chemistry conditions at ambient temperature as well as at elevated temperatures. Series of cyclic potentiodynamic polarization tests were performed to study the localized corrosion resistance of Alloy 800 as a function of chloride ion concentration in the SG crevice solution at 40°C, 150°C and 300°C. Based on the experimental results, empirical equations were provided for calculating the pitting potential of nuclear grade Alloy 800 in the SG secondary side crevice chemistries with different levels of chloride concentration at SG layup, startup and operating temperatures.</jats:p> Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions AECL Nuclear Review |
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Canadian Nuclear Laboratories Limited, 2012 |
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Canadian Nuclear Laboratories Limited, 2012 |
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AECL Nuclear Review |
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| title |
Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| title_unstemmed |
Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| title_full |
Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| title_fullStr |
Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| title_full_unstemmed |
Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| title_short |
Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| title_sort |
localized corrosion of nuclear grade alloy 800 under steam generator layup, startup and operating conditions |
| topic |
General Medicine |
| url |
http://dx.doi.org/10.12943/anr.2012.00003 |
| publishDate |
2012 |
| physical |
13-20 |
| description |
<jats:p>The localized corrosion resistance of nuclear-grade Alloy 800, which is one of the preferred steam generator (SG) heat exchange tube materials of CANDU and PWR reactors, was studied under simulated SG secondary side crevice chemistry conditions at ambient temperature as well as at elevated temperatures. Series of cyclic potentiodynamic polarization tests were performed to study the localized corrosion resistance of Alloy 800 as a function of chloride ion concentration in the SG crevice solution at 40°C, 150°C and 300°C. Based on the experimental results, empirical equations were provided for calculating the pitting potential of nuclear grade Alloy 800 in the SG secondary side crevice chemistries with different levels of chloride concentration at SG layup, startup and operating temperatures.</jats:p> |
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| description | <jats:p>The localized corrosion resistance of nuclear-grade Alloy 800, which is one of the preferred steam generator (SG) heat exchange tube materials of CANDU and PWR reactors, was studied under simulated SG secondary side crevice chemistry conditions at ambient temperature as well as at elevated temperatures. Series of cyclic potentiodynamic polarization tests were performed to study the localized corrosion resistance of Alloy 800 as a function of chloride ion concentration in the SG crevice solution at 40°C, 150°C and 300°C. Based on the experimental results, empirical equations were provided for calculating the pitting potential of nuclear grade Alloy 800 in the SG secondary side crevice chemistries with different levels of chloride concentration at SG layup, startup and operating temperatures.</jats:p> |
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| imprint | Canadian Nuclear Laboratories Limited, 2012 |
| imprint_str_mv | Canadian Nuclear Laboratories Limited, 2012 |
| institution | DE-Gla1, DE-Zi4, DE-15, DE-Rs1, DE-Pl11, DE-105, DE-14, DE-Ch1, DE-L229, DE-D275, DE-Bn3, DE-Brt1, DE-Zwi2, DE-D161 |
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| physical | 13-20 |
| publishDate | 2012 |
| publishDateSort | 2012 |
| publisher | Canadian Nuclear Laboratories Limited |
| record_format | ai |
| recordtype | ai |
| series | AECL Nuclear Review |
| source_id | 49 |
| spelling | Lu, Y. 1929-8056 1929-6371 Canadian Nuclear Laboratories Limited General Medicine http://dx.doi.org/10.12943/anr.2012.00003 <jats:p>The localized corrosion resistance of nuclear-grade Alloy 800, which is one of the preferred steam generator (SG) heat exchange tube materials of CANDU and PWR reactors, was studied under simulated SG secondary side crevice chemistry conditions at ambient temperature as well as at elevated temperatures. Series of cyclic potentiodynamic polarization tests were performed to study the localized corrosion resistance of Alloy 800 as a function of chloride ion concentration in the SG crevice solution at 40°C, 150°C and 300°C. Based on the experimental results, empirical equations were provided for calculating the pitting potential of nuclear grade Alloy 800 in the SG secondary side crevice chemistries with different levels of chloride concentration at SG layup, startup and operating temperatures.</jats:p> Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions AECL Nuclear Review |
| spellingShingle | Lu, Y., AECL Nuclear Review, Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions, General Medicine |
| title | Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| title_full | Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| title_fullStr | Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| title_full_unstemmed | Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| title_short | Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| title_sort | localized corrosion of nuclear grade alloy 800 under steam generator layup, startup and operating conditions |
| title_unstemmed | Localized Corrosion of Nuclear Grade Alloy 800 Under Steam Generator Layup, Startup and Operating Conditions |
| topic | General Medicine |
| url | http://dx.doi.org/10.12943/anr.2012.00003 |