Acknowledgement
This work was financially supported by Korea Hydro & Nuclear Power Co. Ltd. (KHNP) (Contract No. 22-Tech-4).
References
- G. Koch, J. Varney, N. Thompson, O. Moghissi, M. Gould, J. Payer, International Measures of Prevention, Application, and Economics of Corrosion Technologies Study, NACE International, Houston TX, 2016. March 1.
- Nuclear Energy for a Net Zero World, International Atomic Energy Agency, Vienna, September, 2021.
- R.W. Staehle, J.A. Gorman, Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: Part 1, Corrosion 59 (11) (2003) 931-994.
- R.W. Staehle, J.A. Gorman, Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: Part 2, Corrosion 60 (1) (2004) 5-63.
- R.W. Staehle, J.A. Gorman, Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: Part 3, Corrosion 60 (2) (2004) 115-180.
- R. Kilian, R. Zimmer, R. Arenz, J. Beck, T. Schonherr, M. Widera, Operating experience with alloy 800 SG tubing in europe, in: Proc. 13th International Conference on Environmental Degradation in Nuclear Power Systems - Water Reactors, 2007. Whistler, British Columbia, Canada, April 19-23.
- Steam Generator Management Program: Alloy 800 Steam Generator Tubing Experience, Electric Power Research Institute, Palo Alto, CA, 2012 1024992.
- S.D. Cramer, B.C. Covino (Eds.), ASM Handbook Volume 13A Corrosion: Fundamentals, Testing, and Protection, ASM International, Materials Park, OH, 2003.
- M.G. Fontana, N.D. Greene, Corrosion Engineering, McGraw Hill Higher Education, 1978.
- J.W. Oldfield, W.H. Sutton, Crevice corrosion of stainless steels: I. A mathematical model, J. British Corrosion V- 13 (1) (1978) 13-22.
- R.K. Dayal, "Ch.4-Crevice corrosion of stainless steel in corrosion of austenitic strainless steels: mechanism, in: H.S. Khatak, B. Raj (Eds.), Mitigation and Monitoring, 2002, pp. 106-116.
- A. Alavi, R.A. Cottis, The determination of pH, potential, and chloride concentration in corroding crevices on 304 stainless steel and 7475 aluminum alloy, Corrosion Sci. 27 (5) (1987) 443-451.
- C.J. Semino, J.R. Galvele, Passivity breakdown of high purity iron and AISI 4340 steel in 0.5M NaCl solution, Corrosion Sci. 16 (1976) 297-306.
- J.M. Silcock, Effect of acidity and applied potential on the stress corrosion cracking of type 316 austenitic steel in MgCI2, Br. Corrosion J. 14 (4) (1979) 206-215.
- H. Leinonen, T. Schildt, H. Hanninen, Stress corrosion cracking-crevice interaction in austenitic stainless steels characterized by acoustic emission, Metallurgical and Materials Transaction A (42A) (2011) 424-433.
- H.W. Pickering, Significance of the local electrode potential within pits, crevices and cracks, Corrosion Sci. 29 (1989) 325-341.
- B.D. Force, H. Pickering, A clearer view of how crevice corrosion occurs, J. Metal, September (1995).
- Yuan Xu, H.W. Pickering, The initial potential and current distribution in the crevice corrosion process, J. Electrochem. Soc. 140 (3) (1993) 658-668.
- Y.-J. Kim, P.L. Andresen, Data quality, issues, and guidelines for electrochemical corrosion potential measurement in high temperature water, Corrosion 59 (7) (2003) 584-596.
- Y.-J. Kim, Effect of water chemistry on corrosion behavior of 304SS in 288℃ water, in: International Conference on Water Chemistry of Nuclear Reactor Systems, EPRI, San Francisco, CA, 2004. October 11-14.
- Y.-J. Kim, Electrochemical interactions of hydrogen, oxygen, and hydrogen peroxide on metal surfaces in high temperature, high purity water, in: Proc. 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, TMS, 1997, pp. 641-648. August 10-14, Amelia Island, FL.
- Y.-J. Kim, P.L. Andresen, "Catalytic response and electrode kinetics on noble metal-treated type 304 stainless steel in 288℃ water, Corrosion 56 (12) (2000) 1242-1249.
- Y.-J. Kim, L.W. Niedrach, P.L. Andresen, Corrosion potential behavior of noble metal-modified alloys in high temperature water, Corrosion 52 (10) (1996) 738-742.
- F.P. Ford, P.L. Andresen, Corrosion in nuclear systems: environmentally assisted cracking in light water reactors, in: P. Marcus, J. Ouder (Eds.), Corrosion Mechanisms, Marcel Dekker, 1994, pp. 501-546.
- P.L. Andresen, Y.-J. Kim, Developments in SCC mitigation by electrocatalysis, in: Proc. 15th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, Colorado Springs, CO, August 7-11, 2011, pp. 1967-1988.
- C.B. Bahn, S.H. Oh, B.G. Park, I.S. Hwang, I.H. Rhee, U.C. Kim, J.W. Na, Impurity concentration behaviors in a boiling tubesheet crevice: Part II. Packed crevice, Nucl. Eng. Des. 225 (2003) 145-157.
- Computer-calculated potential pH diagrams to 300oC, EPRI NP-3137 2 (1983). EPRI, June.
- C.B. Bahn, K.E. Kazsa, J. Park, W.J. Shack, "Experimental simulation of Na and Cl hideout in steam generator crevices ", Nucl. Eng. Des. 250 (2012) 156-166.
- Y. Wada, K. Ishida, M. Tachibana, M. Aizawa, M. Fuse, Hydrazine and hydrogen Co-injection to mitigate stress corrosion cracking of structural materials in boiling water reactors (VII) - effects of bulk water chemistry on ECP distribution inside a crack, J. Nucl. Sci. Technol. (Tokyo, Jpn.) 44 (11) (2007) 1448-1457.
- D.F. Taylor, Crevice corrosion of alloy 600 in high temperature aqueous environments, Corrosion 35 (12) (1979) 550-559.
- D. Chen, X. Wu, E. Han, Crevice corrosion behavior of nuclear-grade 304 stainless steel in 290 ℃ pure water, in: 4th. International Symposium on Materials and Reliability in Nuclear Power Plants, 2015, pp. 20-23, 349, Sep 2015, Shenyang, China, Sep.
- Y. Wada, A. Watanabe, K. Ishida, M. Tachibana, N. Shigenaka, N. Kawashima, Local radiolysis and electrochemical corrosion potential in crevice environment, in: NPC 2012-Nuclear Chemistry Conference: 9th International Workshop on Radiolysis, Electrochemistry and Materials Performance, 2012. September 24-27, Paris, France.
- H.P. Seifert, S. Ritter, "The influence of ppb levels of chloride impurities on the stress corrosion crack growth behaviour of low-alloy steels under simulated boiling water reactor conditions, Corrosion Sci. 108 (2016) 134-147.
- EPRI, BWRVIP-190 Revision 1: BWR Vessel and Internals Project, Volume 1: BWR Water Chemistry Guidelines - Mandatory, Needed, and Good Practice Guidance, EPRI, Palo Alto, CA, 2014.
- S.J. Zinkle, G.S. Was, Materials challenges in nuclear energy, Acta Mater. 61 (2013) 735-758.
- D.F. Taylor, M. Silverman, Some effects of electrolyte composition and heat treatment on the aqueous crevice corrosion of alloy 600 and type 304 stainless steel at 288℃, Corrosion 36 (8) (1980) 447-458.
- F. Ning, J. Tan, Z. Zhang, X. Wang, X. Wu, E.-H. Han, W. Ke, Crevice corrosion behavior of alloy 690 in high-temperature aerated chloride solution, Materials 15 (2022) 5434-5446.
- W.L. Marshall, E.V. Jones, J. Physical, Chemistry 70 (1966) 4028.
- W.J. Shack, T.F. Kassner, P.S. Maiya, J.Y. Park, W.E. Ruther, Environmental assisted cracking in light water reactors, in: NRC NUREG/CR-4667 Vol.1 & II, Argonne Nat Labs, 1986. ANL-86-31 and ANL-86-37.
- C.C. Lin, Radiochemistry in Nuclear Power Reactors, Nuclear Science Series, NASNS-3119, National Academy Press, Washington D.C., 1996.
- Y.-J. Kim, G.D. Song, S.H. Baek, B.K. Kim, J.S. Cheon, J.H. Kim, H.-S. Shim, S.-H. Jeon, H. Kim, Radiochemical behavior of nitrogen species in high temperature water, Nucl. Eng. Technol. 55 (2023) 3183-3193.