|
參考文獻 1. Ford, P., Stress Corrosion Cracking of Low Alloy Steels Under BWR Conditions; Assessment of CHR Algorithms, in International Symposium on Environment Degradation of Materials in Nuclear Power Systems-Water Reactors1999. 2. Barberis, P., T. Merle-Mejean, and P. Quintard, On Raman Spectroscopy of Zirconium Oxide Films. Journal of Nuclear Materials, 1997. 246: p. 232-243. 3. Andresen, P., Emerging Issues and Fundamental Processes in Environmental Cracking in Hot Water, in National Association of Corrosion Engineers2007, NACE International: Nashville, Tennessee. 4. Sugama, J., S. Uchida, and N. Yamashiro, Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (II) Evaluation of Oxide Film Properties by Complex Impedance Measurement. Journal of Nuclear Science and Technology, 2004. 41: p. 880-889. 5. Jayaweera, P., S. Hettiarachchi, and H. Ocken, Determination of High Temperature Zeta Potential and pH of Zero Charge of Some Transition Metal Oxides. Colloids and Surface A: Physicochemical and Engineering Aspects, 1994. 85: p. 19-27. 6. Miyazawa, T., T. Terachi, and S. Uchida, Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (V) Characterization of Oxide Film with Multilateral Surface Analyses. Journal of Nuclear Science and Technology, 2006. 43(8): p. 884-895. 7. Uchida, S., T. Satoh, and J. Sugama, Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (III) Evaluation of Electric Resistance of Oxide Film by Equivalent Circuit Analysis for Frequency Dependent Complex Impedances. Journal of Nuclear Science and Technology, 2005. 42: p. 66-74. 8. Miyazawa, T., S. Uchida, and T. Satoh, Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (IV) Determination of Oxide Film Properties with Multilateral Surface Analyses. Journal of Nuclear Science and Technology, 2005. 42(2): p. 233-241. 9. Uchida, S., Y. Morishima, and T. Hirose, Effects of Hydrogen Peroxide on Corrosion of Stainless Steel (VI) Effects of Hydrogen Peroxide and Oxygen on Anodic Polarization Properties of Stainless Steel in High Temperature Pure Water. Journal of Nuclear Science and Technology, 2007. 44: p. 758-766. 10. Murayama, Y., T. Satoh, and S. Uchida, Effects of Hydrogen Peroxide on Intergranular Stress Corrosion Cracking of Stainless Steel in High Temperature Water, (V). Journal of Nuclear Science and Technology, 2002. 39: p. 1199-1206. 11. Kessides, I.N., The future of the nuclear industry reconsidered: Risks, uncertainties, and continued promise. Energy Policy, 2012. 12. Zinkle, S.J. and G. Was, Materials challenges in nuclear energy. Acta Materialia, 2013. 61(3): p. 735-758. 13. Light Water Reactor Sustainability Program: Integrated Program Plan, INL/EXT-11-23452. Office of Nuclear Energy. US Department of Energy; 2012. 14. Grimes RW, Konings RJM, Edwards L. Greater tolerance for nuclear materials. Nature Mater 2008;7:683. 15. Guerin Y, Was GS, Zinkle SJ. Materials challenges for advanced nuclear energy systems. MRS Bull 2009;34:10. 16. Zinkle SJ, Busby JT. Structural materials for fission and fusion energy. Mater Today 2009;12:12. 17. Garner FA, Toloczko MB, Sencer BH. J Nucl Mater 2000;276:123. 18. Was GS. Fundamentals of radiation materials science. New York: Springer; 2007. 19. Zinkle SJ. Phys Plasmas 2005;12:058101. 20. Schilling W, Ullmaier H. In: Frost BRT, editor. Materials science and technology: a comprehensive treatment. Nuclear materials. vol. 10B. Weinheim: VCH; 1994. p. 179. 21. Zinkle SJ. In: Konings RJM, editor. Comprehensive nuclear materials, vol. 1. Amsterdam: Elsevier; 2012. p. 65. 22. World List of Nuclear Power Plants. Nucl News 2012;55:55. 23. Danko JC. Corrosion in the nuclear power industry. Metals handbook. Corrosion, vol. 13. Metals Park, OH: ASM International; 1987. p. 927. 24. Feron D, Olive J-M, editors. Corrosion issues in light water reactors – stress corrosion cracking. Boca Raton, FL: CRC Press; 2007. 25. S. Uchida et al., “Road Maps on Research and Development Plans for Water Chemistry of Nuclear Power Systems in Japan”, International Conference on Water Chemistry of Nuclear Reactor Systems, Germany, 2008. 26. Tsung-Kuang Yeh and Fang Chu, “An Improved Model for Assessing the Effectiveness of Hydrogen Water Chemistry in Boiling Water Reactors,” Nuclear Science and Engineering, 139, (2001) 221-233. 27. Kaesche, H., Die Korrosion der Metalle physikalisch-chemische Prinzipien und aktuelle Probleme. 1990: Springer. 28. Winkler, R., F. Huttner, and F. Michel, Senkung der Korrosionsrate im Primarkreislauf von Druckwasserreaktoren zur Begrenzung radioaktiver Ablagerungen. VGB Kraftwerkstechnik, 1989. 69: p. 524-531. 29. Winkler, R. and H. Lehmann, Zur Qualitätsbewertung oxidischer Korrosionsschutzschichten. VGB Kraftwerkstechnik, 1985. 65: p. 421-426. 30. Asakura, Y., et al., Relationships Between Corrosion Behavior of AISI 304 Stainless Steel in High-Temperature Water and Its Oxide Film Structure. Corrosion, 1989. 45: p. 119-124. 31. Kim, Y.J., Analysis of Oxide Film Formed on Type 304 Stainless Steel in 288oC Water Containing Oxygen, Hydrogen, and Hydrogen Peroxide. Corrosion, 1999. 55. 32. Kim, Y.J., Effect of Water Chemistry on Corrosion Behavior of 304 SS in 288℃ Water, in International Water Chemistry Conference2004: San Francisco. 33. Stellwag, B., The Mechanism of Oxide Film Formation on Austenitic Satinless Steels in High Temperature Water. Corrosion Science, 1998. 40: p. 337-370. 34. Lister, D.H., R.D. Davison, and E. McAlpine, The mechanism and kinetics of corrosion product release from stainless steel in lithiated high temperature water. Corrosion Science, 1987. 27: p. 113-140. 35. Leistikow, S. and R. Kraft, Verbesserung der Heißdampf-Korrosionsbeständigkeit von Incoloy Alloy 800-Rohrmaterial durch verformende Oberflächenvorbehandlungen. Werkstoffe und Korrosion, 1974. 25(1): p. 12-25. 36. Robertson, J., The mechanism of high temperature aqueous corrosion of steel Corrosion Science, 1989. 29: p. 1275-1291. 37. Lin, C.C., F.R. Smith, and R.L. Cowan, Effects of Hydrogen Water Chemistry on Radiation Field Buildup in BWRs. Nuclear Engineering and Design, 1996. 166: p. 31-36. 38. Cheng, Y.F. and F.R. Steward, Corrosion of carbon steels in high-temperature water studied by electrochemical techniques. Corrosion Science, 2004. 46: p. 2405-2420. 39. Kumai, C.S. and T.M. Devine, Oxidation of Iron in 288°C, Oxygen-Containing Water. Corrsion, 2005. 61: p. 201-218. 40. Taylor, D.F., Corrosion, 1979. 35: p. 550-. 41. Beverskog, B. and I. Puigdomenech, Pourbaix Diagrams for the Ternary System of Iron-Chromium-Nickel. Corrosion, 1999. 55: p. 1077-1087. 42. Wada, Y., A. Watanabe, and M. Tachibana, Effects of Hydrogen Peroxide on Intergranular Stress Corrosion Cracking of Stainless Steel in High Tmeperature Water, (IV) Effects of Oxide Film on Electrochemical Corrosion Potential. Jounal of Nuclear Science and Technology, 2001. 38: p. 183-192. 43. Kim, Y.J., In-Situ Electrochemical Impedance Measurement of Oxide Film Formed on Type 304 Stainless Steel in High-Temperature Water. Corrosion, 2000. 56: p. 389-394. 44. Pathania, P., Zirconium Oxide Deposition to Mitigate IGSCC, in BWRVIP Mitigation Committee Meeting1997: Atlanta. 45. Ganguli, D. and D. Kundu, Preparation of Amorphous ZrO2 Coatings from Metal-Organic Solutions. Journal of Materials Science Letters, 1984. 3: p. 503-504. 46. Kim, Y.J. and P.L. Andresen, Application of Insulated Protective Coatings for Reduction of Corrosion Potential of Type 304 Stainless Steel in High-Temperature Water. Corrosion, 1998. 54: p. 1012-1017. 47. Zhou, X., I. Balachov, and D.D. MaDonald, The Effect of Dielectric Coatings on IGSCC in Sensitized Type 304SS in High Temperature Dilute Sodium Sulfate Solution. Corrosion Science, 1998. 40: p. 1349-1362. 48. Zhou, Z.F., E. Chalkova, and S.N. Lvov, Development of a hydrothermal deposition process for applying zirconia coatings on BWR materials for IGSCC mitigation. Corrosion Science, 2007. 49: p. 830-843. 49. Yeh, T.K., M.Y. Lee, and C.H. Tsai, Intergranular Stress Corrosion Cracking of Type 304 Stainless Steels Treated with Inhibitive Chemicals in Simulated Boiling Water Reactor Environments. Journal of Nuclear Science and Technology, 2002. 39: p. 531-539. 50. Yeh, T.K., C.T. Liu, and C.H. Tsai, The Influence of ZrO2 Treatment on the Electrochemical Behavior of Oxygen and Hydrogen on Type 304 Stainless Steels in High Temperature Water. Journal of Nuclear Science and Technology, 2005. 42: p. 809-815. 51. Yeh, T.K., C.H. Tsai, and Y.H. Cheng, The Influence of Dissolved Hydrogen on the Corrosion of Type 304 Stainless Steels Treated with Inhibitive Chemicals in High Temperature Pure Water. Journal of Nuclear Science and Technology, 2005. 42: p. 462-469. 52. Yeh, T.K., Y.C. Chien, and B.Y. Wang, Electrochemical Characteristics of Zirconium Oxide Treated Type 304 Stainless Steels of Different Surface Oxide Structures in High Temperature Water. Corrosion Science, 2008. 50: p. 2327-2337. 53. Atik, M. and M.A. Aegerter, Corrosion resistant sol-gel ZrO2 coatings on Stainless Steel. Journal of Non-Crystalline Solids, 1992. 147&148: p. 813-819. 54. Zhou, Z.F., Optimization of Zirconium Oxide Coating Technology to Mitigate IGSCC in BWRs, in BWRVIP Mitigation Committee Meeting2002. 55. Stellwag, B. and R. Kilian, Investigations into Chemistry-Related Alternatives to Hydrogen Water Chemistry in BWR Plants, in International Workshop on LWR Cooloant Water Radiolysis & Electrochemistry2000. 56. Hunter, R.J., Zeta Potential in Colloid Science : Principles and Applications. 1988: Academic Press. 57. C. C. Lin, F. R. Smith, "Decomposition of Hydrogen Peroxide at Elevated Temperature," EPRI Report NP-6733 (1990). 58. D. D. Macdonald et al., "Corrosion Potential Measurements on Type 304 SS and Alloy 182 in Simulated BWR Environments," Corrosion-January (1993) 8-16. 59. Anders Molander and Mats Ullberg, "The Corrosion Potential of Stainless Steel in BWR Environment Comparison of Data and Modeling Results," Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asi a(2003). 60. N. Hiraide, K. Sugimoto, "Degradation of nitride, carbide and oxide ceramics materials in high temperature aqueous solutions," Boshoku Gijyutsu, 37, 415 (1988). 61. T. Kawakubo, H. Hirayama, A. Goto et al., "corrosion behavior of ceramics in high purity water at 290oC," Zairyo, 38, 300(1989). 62. Young-Jin Kim and Peter L. Andresen, "Application of Insulated Protective Coating for 304 SS SCC Mitigation in 288oC Water," 11th Int. Conf. Environmental Degradation of Materials in Nuclear Systems (2003). 63. Kazushige ISHIDA et al., "Effects of Flow Rate on Dissolution of Monocrystal Aluminaand Monocrystal Yttria-Stabilized Zirconia in High-Temperature Pure Water, " Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 46, No. 12, p. 1120–1128(2009). 64. Garcia, S.E., J.F. Giannelli, and M.L. Jarvis, Advances in BWR Water Chemistry, in Nuclear Plant Chemistry2012: Paris, France. 65. Varela, J.A., E.W. Davis, and T.A. Caine, Plant Chemistry Response to On-Line NobleChem, in Nuclear Plant Chemistry2012: Paris, France. 66. Garcia, S.E., A.D. Odell, and J.F. Giannelli, Early Hydrogen Water Chemistry in the Boiling Water Reactor: Industry-First Demonstration, in Nuclear Plant Chemistry Conference2012: Paris, France. 67. Abe, A. and H. Tobita, Mitigation of SCC Initation on BWR Core Internals by Means of Hydrogen Water Chemistry During Start-up. Nuclear Science and Engeering, 2005. 149: p. 312-324. 68. Stellwag, B., M. Pop, and B. Devrient, Effect of UV Irradiation on Low Concentration Methanol Solution in BWR Condition Loop Testing, in Nuclear Plant Chemistry2012: Paris, France. 69. Andresen, P.L., Factors Governing the Prediction of LWR Component SCC Behavior From Laboratory Data, in National Association of Corrosion Engineers1999, NACE Interantional: San Antonio, Tx. 70. Jr., W.D.C., Materials Science and Engineering - An Introduction, 5th Edition. 1999. 71. Chung, P.C.-K., Quantitative Study of the Degree of Sensitization of Austenitic Stainless Steel by Electrochemical Measurements. 1979: Ohio State University. 72. Busby, J.T., G.S. Was, and E.A. Kenik, Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels. Journal of Nuclear Materials, 2002. 302(1): p. 20-40. 73. Wilde, B.E., Stress Corrosion Cracking. Vol. Failure Analysis and Prevention. 1986: American Society for Metals. 203. 74. Uhlig, H.H. and R.W. Revie, Corrosion and corrosion control, ed. 3. 1985. 75. Ford, P., Development and Use of a Predictive Model of Crack Propagation in 304/316L, A533B/A508 and Inconel 600/182 Alloys in 288oC water, in Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors1988. 76. Angeliu, T.M., P.L. Andresen, and F.P. Ford, Apolying Slip-Oxidation to the SCC of Austenitic Materials in BWR/PWR Environments in National Association of Corrosion Engineers1998, NACE International: San Diego Ca. 77. Ford, F. and P. Andresen, Corrosion in Nuclear Systems: Environment Assisted Cracking in Light Water Reactors, 1994: New York. p. 501-546. 78. Kazushige, I., W. Yoichi, and T. Masahiko, Hydrazine and Hydrogen Co-injection to Mitigate Stress Corrosion Cracking of Structural Materials in Boiling Water Reactors, (II) Reactivity of Hydrazine with Oxidant in High Temperature Water under Gamma-irradiation. Journal of Nucler Science and Technology, 2006. 79. Macdonald, D., Theoretical Estimation of Crack Growth Rates in Type 304 Stainless Steel in Boiling-Water Reactor Coolant Environment. Corrosion, 1996. 52. 80. Herbert H. Uhlig & R. Winston Revie , Corrosion and Corrosion Control, Chapter 7.
|