Comprehensive nuclear materials 5 05 corrosion and stress corrosion cracking of austenitic stainless steels

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Comprehensive nuclear materials 5 05   corrosion and stress corrosion cracking of austenitic stainless steels

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Comprehensive nuclear materials 5 05 corrosion and stress corrosion cracking of austenitic stainless steels Comprehensive nuclear materials 5 05 corrosion and stress corrosion cracking of austenitic stainless steels Comprehensive nuclear materials 5 05 corrosion and stress corrosion cracking of austenitic stainless steels Comprehensive nuclear materials 5 05 corrosion and stress corrosion cracking of austenitic stainless steels Comprehensive nuclear materials 5 05 corrosion and stress corrosion cracking of austenitic stainless steels

r temporarily because of startups, for example Different systems during shutdown may be filled with air, and this may cause air pockets during startup The oxygen from air will then dissolve into the primary water and local oxidizing conditions temporarily emerge until the oxygen is consumed by the oxidation of metal surfaces The risk of pitting corrosion (and TGSCC) is, however, highest in auxiliary systems, for example, at outer surfaces, where the temperature is low enough for condensation to occur Thus, pitting corrosion can occur at nominally dry locations Accumulation of aggressive local conditions is enhanced by crevices The sources of chlorides were listed earlier Sulfate sources have been introduced earlier, for example, in molybdenum disulfide greases, but since the harmful influence of this material was identified, it is not an allowed expendable material Again, copper can enter the system from copper-containing structural components Pitting corrosion is seldom considered to pose a safety problem, as the wall thicknesses of pressure boundary components are usually large enough to sustain pitting corrosion for long times without leakage However, pitting corrosion is always an indication of a harmful environment existing at the location and is often associated with the risk of TGSCC, which can cause wall cracking in short time periods Pitting corrosion enhances the risk of SCC as the pits increase the local stress concentration and thus act as crack initiators Observation of pitting corrosion shall therefore not be omitted as insignificant 5.05.3 Pitting Corrosion Pitting corrosion occurrence has several similarities to TGSCC, that is, it requires oxidizing conditions and presence of water with harmful ions, such as chlorides, fluorides, sulfates, and/or copper, but no stress is needed The Type 304 stainless steel is more prone to pitting corrosion than Type 316 stainless steel Pitting corrosion 5.05.4 Microbiologically Induced Corrosion A rather rare corrosion mode is microbiologically induced corrosion, or nowadays, microbiologically influenced corrosion (MIC) MIC is normal Corrosion and Stress Corrosion Cracking of Austenitic Stainless Steels electrochemical corrosion where the microorganisms either chemically or physically change the conditions on the metal surface to be favorable to corrosion.59 MIC appears as localized corrosion rather than as uniform corrosion, and in welds rather than in base materials Pitting corrosion in the weld metal can cause preferential attack of either the austenite or the ferrite phase of the weld metal The microorganisms of interest in MIC are mostly bacteria and fungi The highest risk of MIC is at temperatures from 15 to 45  C and near neutral pH, that is, in the range from to MIC has been observed in fire-fighting systems, for example MIC is stopped with great difficulty once it is established due to the high sustainability of the microorganisms involved The quality of the water in all phases of the lifetime of the equipment is, thus, very important at locations with risk of MIC Water of high quality must be used, not only during normal operation, but also during hydrotesting of the system, for example 13 14 15 16 17 18 19 20 21 22 References 10 11 12 Peckner, D.; Bernstein, I M Handbook of Stainless Steels; McGraw-Hill: New York, 1977; pp 4-35–4-53, 751–757 Ford, P F In Proceedings of 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Whistler, BC, Canada, Aug 19–23, 2007; Allen, T R., et al Eds.; Canadian Nuclear Society: Toronto, ON, 2007 NRC Expert Panel Report on Proactive Management of Materials Degradation; NUREG/CR-6923; US Nuclear Regulatory Commission: Washington, DC, 2007 Shah, V N.; MacDonald, P E Aging and Life Extension of Major Light Water Reactor Components; Elsevier: Amsterdam, 1993 ASTM Standard A 262-02a Standard Practices for Detecting Susceptibility to Intergranular Attack in Austenitic Stainless Steels; ASTM International: West Conshohocken, PA, 2008; p 17 ASTM Standard G 108-94 Standard Test Method for Electrochemical Reactivation (EPR) for Detecting Sensitization of AISI Type 304 and 304L Stainless Steels; ASTM International: West Conshohocken, PA, 2004 Folkhard, E Welding Metallurgy of Stainless Steel; 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pp 365–376 Yamashita, H.; Ooki, S.; Tanaka, Y.; Takamori, K.; Asano, K.; Suzuki, S Int J Press Vess Pip 2008, 85, 582–592 Andresen, P L Corrosion 1988, 44(7), 450 Andresen, P L In Proceedings of 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Lake Tahoe, NV, Aug 5–9, 2001; Ford, F P., Was, G., Eds.; NACE International: Houston TX, 2001; p Andresen, P.; Angeliu, T.; Catlin, W.; Young, L.; Horn, R In Corrosion, 2000, NACE 55th Annual Conference, Orlando, FL, Mar 26–31, 2000; p 12, Paper No 00203 Andresen, P L.; Emigh, P.; Morra, M.; Horn, R In Proceedings of 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Stevenson, WA, Aug 11–14, 2003; American Nuclear Society: La Grange Park, IL, 2003; pp 816–833 104 Corrosion and Stress Corrosion Cracking of Austenitic Stainless Steels 32 Andresen, P L.; Morra, M M J Nucl Mater 2008, 383(1–2), 97–111 33 Horn, R.; Gordon, G.; Ford, P.; Cowan, R Nucl Eng Des 1997, 174, 313–325 34 Magdowski, R.; Speidel, M O In Corrosion ’96, NACE, 51st Annual Conference and Exposition, Denver, CO, Mar 24–29 1996; p 6, Paper No 112 35 Taăhtinen, S.; Haănninen, H.; Trolle, M In Proceedings of the 6th Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, San Diego, CA, Aug 1–5, 1993; Gold, R E., Simonen, E P., Eds.; TMS: Warrendale, PA, 1993 36 Prevey, P S.; Jayaraman, N In Proceedings of ICSP 9, Paris, Marne la Vallee, France, Sept 6–9, 2005; p 7, Paper No 260 37 Offer, H P.; Morra, M.; Chan, A In Proceedings of 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Whistler, BC, Canada, Aug 19–23, 2007; Allen, T R., et al Eds.; Canadian Nuclear Society: Toronto, ON, 2007; p 17 38 Robertson, J Corros Sci 1991, 32, 443–465 39 Stellwag, B Corros Sci 1998, 40, 337–370 40 Ford, P.; Taylor, D.; Andresen, P.; Ballinger, R Corrosion Assisted Cracking of Stainless Steel and Low Alloys Steel in LWR Environments; Report NP5064S; Electric Power Research Institute: Palo Alto, CA, 1987; p 124 41 Ford, P F.; Andresen, P L In Corrosion Mechanisms in Theory and Practice; Marcus, P., et al Ed.; Marcel Dekker: New York, 1995; pp 501–546 42 Hettiarachchi, S In Proceedings of 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Stevenson, WA, Aug 11–14, 2003; American Nuclear Society: La Grange Park, IL, 2003; pp 477–487 43 Hettiarachchi, S In Proceedings of 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Lake Tahoe, NV, Aug 5–9, 2007; Ford, F P., Was, G., Eds.; NACE International: Houston, TX, 2007; p 10 44 Andresen, P L Personal communication, May 2009 45 Andresen, P L In Proceedings of 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Monterey, CA, Aug 25–29, 1995, American Nuclear Society: La Grange Park, IL, 1995; pp 209–218 46 General Electric Company Alternative Alloys for BWR Pipe Application; NP-2671-LD, Final Report; San Jose, CA, 1982 47 Haănninen, H.; Aho-Mantila, I In Proceedings of 3rd International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Traverse City, MI, Aug 30–Sept 3, 1987; TMS–AIME: Warrendale, PA, 1987; pp 77–92 48 49 50 51 52 53 54 55 56 57 58 59 Erve, M.; Wesseling, U.; Kilian, R.; et al In 20th MPA-Seminar, Stuttgart, Oct 67, 1994; Staatliche Materialpruăfungsanstalt (MPA) Universitaăt Stuttgart: Stuttgart, Germany, 1994; Vol p 21, Paper No 29 Kilian, R In Proceedings of 7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Breckenridge, CO, Aug 7–10, 1995; Airey, G., Ed.; NACE International: Houston, TX, 1995; pp 529–540 Kilian, R.; Eberle, U.; Bruămmer, G.; et al In Proceedings of the 9th Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Newport Beach, CA, Aug 1–5, 1999; Bruemmer, S M., Ford, F P., Was, G S., Eds.; TMS–AIME: Warrendale, PA, 1999; pp 347–357 International Atomic Energy Agency Mitigation of Intergranular Stress Corrosion Cracking in RBMK Reactors; Final Report of the Programme’s Steering Committee; IAEA-EBP-IGSCC; IAEA: Vienna, 2002 Timofeev, B.; Fedorova, V.; Buchatskii, A Mater Sci 2004, 40(1), 48–59 Scott, P M In Proceedings of 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Newport Beach, CA, Aug 1–5, 1999; Ford, F P., Bruemmer, S M., Was, G S., Eds.; TMS–AIME: Warrendale, PA, 1999 Couvant, T.; Legras, L.; Pokor, C.; et al In Proceedings of 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Whistler, BC, Canada, Aug 19–23, 2007; Allen, T R., et al Eds.; Canadian Nuclear Society: Toronto, ON, 2007; Vol pp 499–514 Chynoweth, J.; Hyres, J In Proceedings of 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Whistler, BC, Canada, Aug 19–23, 2007; Canadian Nuclear Society: Toronto, ON, 2007; Vol 2, pp 1214–1225 Kilian, R.; Wesseling, U.; Wachter, O.; Widera, M.; Bruămmer, G.; Ilg, U In Fontevraud V; Sept 23–27, 2002; SFEN: France, 2002 Berge, P.; Keroulas, F.; Gras, J.; Noeăl, D.; Da Vunha Belo, M In Proceedings of 4th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Jekyll Island, GA, Aug 6–10, 1989; Cubicciotti, D., Ed.; NACE International: Houston, TX, 1989; pp 11-74–11-87 McDonald, D.; Cragnolino, G.; Olemacher, J.; Chen, T.; Dhawale, S Intergranular Stress Corrosion Cracking of Austenitic Stainless Steels in PWR Acid Storage Systems; EPRI NP-2531; Electric Power Research Institute: Palo Alto, CA, 1982 Cramer, S., Covino, B., Jr., Moosbrugger, C Eds Handbook Volume 13A: Corrosion Fundamentals, Testing and Protection; ASM International: Materials Park, OH, 2003 .. .Corrosion and Stress Corrosion Cracking of Austenitic Stainless Steels electrochemical corrosion where the microorganisms either chemically... Nuclear Society: La Grange Park, IL, 2003; pp 816–833 104 Corrosion and Stress Corrosion Cracking of Austenitic Stainless Steels 32 Andresen, P L.; Morra, M M J Nucl Mater 2008, 383(1–2), 97–111... pp 1 1-7 4–1 1-8 7 McDonald, D.; Cragnolino, G.; Olemacher, J.; Chen, T.; Dhawale, S Intergranular Stress Corrosion Cracking of Austenitic Stainless Steels in PWR Acid Storage Systems; EPRI NP-2531;

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  • 5.05 Corrosion and Stress Corrosion Cracking of Austenitic Stainless Steels

    • 5.05.1 Introduction to Austenitic Stainless Steels

      • 5.05.1.1 Types, Mechanical Properties, and Microstructures

      • 5.05.1.2 Welding

      • 5.05.1.3 Components Made of Stainless Steels in BWRs and PWRs

      • 5.05.2 Stress Corrosion Cracking

        • 5.05.2.1 IGSCC in BWR Environment

          • 5.05.2.1.1 Degree of sensitization

          • 5.05.2.1.2 Deformation

          • 5.05.2.1.3 Environment

          • 5.05.2.1.4 Stress

          • 5.05.2.1.5 Components at risk

          • 5.05.2.2 IGSCC in PWR Environment

          • 5.05.2.3 TGSCC in BWR and PWR Environments

          • 5.05.3 Pitting Corrosion

          • 5.05.4 Microbiologically Induced Corrosion

          • References

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