The Effects of Metallurgical Factors on PWSCC Crack Growth Rates in TT Alloy 690 in Simulated PWR Primary Water
详细信息    查看全文
  • 作者:Toshio Yonezawa ; Masashi Watanabe…
  • 刊名:Metallurgical and Materials Transactions A
  • 出版年:2015
  • 出版时间:June 2015
  • 年:2015
  • 卷:46
  • 期:6
  • 页码:2768-2780
  • 全文大小:4,672 KB
  • 参考文献:1.H.R.Copson: Physical Metallurgy of Stress Corrosion Fracture, Interscience, New York, 1959.
    2.H. Coriou, L. Grall, Y. Le Gall, and S. Vettier: Third Metallurgy Conference on Corrosion, Saclay, North Holland and Publishing Co., Amsterdam, 1959, pp. 161鈥?9.
    3.H. Coriou, L. Grall, M. Pelras, and S. Vettier: Colloquium of the European Society of Atomic Energy, Studsvick, Sweden, 1962.
    4.H.Coriou, L.Grall, C.Mahieu and M.Pelras : Corrosion, 22 (1966), pp280-290.View Article
    5.H. Coriou, L. Grall, P. Olivier, and H. Willermoz: Proceedings of the Conference on 鈥淔undamental Aspects of Stress Corrosion Cracking鈥? Columbus, 1968, Ohio State University, 1969, pp. 352鈥?9.
    6.H. Schenk: Corrosion 75, 1975, Paper No. 115.
    7.S.J. Green and J.P.N. Paine: Proceedings of the International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Myrtle Beach, SC, August 22鈥?5, 1983, pp. 53鈥?8.
    8.W.H. Bamford and N.A. Palm: Proceedings of the Fourteenth International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, 2009, pp. 1525鈥?6.
    9.T. Yonezawa, K. Onimura, N. Sasaguri, T. Kusakabe, H. Nagano, K. Yamanaka, T. Minami, and M. Inoue: Proceedings of the Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Sept. 9鈥?2, Monterey, CA, 1985, pp. 593鈥?00.
    10.T. Yonezawa, K. Onimura, N. Sasaguri, T. Kusakabe, H. Nagano, K. Yamanaka, T. Minami, and M. Inoue: Proceedings of the International Symposium on Contribution of Materials Investigation to the Resolution of Problems Encountered in PWR Plants, Royal Abbey of Fontevraud, Sept. 2鈥?, 1985, pp. 289鈥?6.
    11.T. Yonezawa, K. Fujimoto, H. Kaguchi, and S. Asada: Proceedings of the 2005 PWSCC of Alloy 600 International Conference and Exhibit Show, Tamaya Resort, Santa Ana Pueblo, NM, March 7鈥?0, 2005.
    12.T. Yonezawa: 鈥淣i Alloys鈥?of Chapter 16, Comprehensive Nuclear Materials, Elsevier, Amsterdam, 2012.
    13.K. Arioka, T. Yamada, T. Miyamoto, and T. Terachi: Proceedings of the International Conference Fontevraud 7, Sept. 26鈥?0, 2010.
    14.D.J. Paraventi and W.C. Moshier: Workshop on Cold Work in Iron and Nickel Base Alloys Exposed to High Temperature Water Environments, Mississauga, June 3鈥?, 2007.
    15.P. Andresen, M. Mora, A. Ahluwalia, and J. Wilson: Proceedings of the 14 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Aug. 23鈥?7, Virginia Beach, VA, 2009, pp. 846鈥?7.
    16.M.B. Toloczko, M.J. Olszta, and S.M. Bruemmer: Proceedings of the 15 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Aug. 7鈥?1, Colorado Springs, CO, 2011, pp. 91鈥?06.
    17.M.B. Toloczko, M.J. Olszta, and S.M. Bruemmer: Proceedings of the 15 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Aug. 7鈥?1, Colorado Springs, CO, 2011, pp. 225鈥?3.
    18.D.R. Tice, S.L. Medway, N. Platts, and J.W. Stairmand: Proceedings of the 15 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Aug. 7鈥?1, Colorado Springs, CO, 2011, pp. 71鈥?7.
    19.B. Alexandreanu, Y. Chen, K. Natesan, and B. Shack: Proceedings of the 15 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Aug. 7鈥?1, Colorado Springs, CO, 2011, pp. 179鈥?6.
    20.Q. Peng, T. Shoji, J. Hou, Y. Takeda, and T. Yonezawa: Proceedings of the 15 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Aug. 7鈥?1, Colorado Springs, CO, 2011, pp. 149鈥?8.
    21.P. Andresen, M. Mora, and A. Ahluwalia: Proceedings of the International Conference Fontevraud 7, Sept. 26鈥?0, 2010.
    22.T. Yonezawa: EPRI MRP Expert Panel Alloy 690 Meeting, Tampa, FL, Dec. 2鈥?, 2009.
    23.T. Yonezawa, T. Horiuchi, N. Sato, and A. Hashimoto: EPRI MRP Expert Panel Alloy 690 Meeting, Tampa, FL, Nov. 29鈥揇ec. 2, 2011.
    24.T. Yonezawa: Proceedings of the 16 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Aug. 11鈥?5, Ashville, NC, CD-Rom, 2013.
    25.K. Arioka, T. Yamada, T. Miyamoto, and T. Terachi: Corrosion, 2011, vol. 67 (3), pp. 035006-1鈥?8.
    26.P. Andresen, P.W. Emigh, M.M. Morra, and R.M. Horn: Proceedings of the 11 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Aug. 10鈥?4, Stevenson, WA, 2003, pp. 816鈥?3.
    27.S. Bruemmer, M. Olszta, and M. Toloczko: Proceedings of the International Conference Fontevraud 7, Sept. 26鈥?0, 2010.
    28.T. Yonezawa, T. Maeguchi, T. Goto, and H. Juan: Proceedings of the 15 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Aug. 7鈥?1, Colorado Springs, Colorado, 2011, pp. 1759鈥?1.
    29.P. Andresen, M.M. Morra, and K. Ahluwalia: Proceedings of the 16 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Aug. 11鈥?5, Ashville, NC, CD-Rom, 2013.
  • 作者单位:Toshio Yonezawa (1)
    Masashi Watanabe (1)
    Atsushi Hashimoto (2)

    1. FRI, New Industry Creation Hatchery Center (NICHe), Tohoku University, 6-6-10, Aoba, Aramaki, Aoba-ku, Sendai, 980-8579, Japan
    2. Kobe Material Testing Laboratory Co, Ltd., 47-13, Niijima, Harima-cho, Kako-Gun, 675-0155, Japan
  • 刊物类别:Chemistry and Materials Science
  • 刊物主题:Chemistry
    Materials Science
    Metallic Materials
    Structural Materials
    Physical Chemistry
    Ceramics,Glass,Composites,Natural Materials
  • 出版者:Springer Boston
  • ISSN:1543-1940
文摘
Primary water stress corrosion cracking growth rates (PWSCCGRs) in highly cold-worked thermally treated (TT) Alloy 690 have been recently reported as exhibiting significant heat-to-heat variability. Authors hypothesized that these significant differences could be due to the metallurgical characteristics of each heat. In order to confirm this hypothesis, the effect of fundamental metallurgical characteristics on PWSCCGR measurements in cold-worked TT Alloy 690 has been investigated. The following new observations were made in this study: (1) Microcracks and voids were observed in or near eutectic crystals of grain boundary (GB) M23C6 carbides (primary carbides) after cold rolling, but were not observed before cold rolling. These primary carbides with microcracks and voids were observed in both lightly forged and as-cast and cold-rolled TT Alloy 690 (heat A) as well as in a cold-rolled TT Alloy 690 (heat Y) that simulated the chemical composition and carbide banded structure of the material previously tested by Paraventi and Moshier. However, this was not observed in precipitated (secondary) M23C6 GB carbides in heavily forged and cold-rolled TT Alloy 690 heat A and a cold-rolled commercial TT Alloy 690. (2) From microstructural analyses carried out on the various TT Alloy 690 test materials before and after cold rolling, the amount of eutectic crystals (primary carbides and nitrides) M23C6 and TiN depended on the chemical composition. In particular, the amount of M23C6 depended on the fabrication process. Microcracks and voids in or near the M23C6 and TiN precipitates were generated by the cold rolling process. (3) The PWSCCGRs observed in TT Alloy 690 were different for each heat and fabrication process. The PWSCCGR decreased with increasing Vickers hardness of each heat. However, for the same heats and fabrication processes, the PWSCCGR increased with increasing Vickers hardness due to cold work. Thus, the PWSCCGR must be affected not only by hardness (or equivalently the cold working ratio) but also by grain size, microcracks, and voids of primary M23C6 carbides, etc., which in turn depend on chemical composition and the fabrication process.

© 2004-2018 中国地质图书馆版权所有 京ICP备05064691号 京公网安备11010802017129号

地址:北京市海淀区学院路29号 邮编:100083

电话:办公室:(+86 10)66554848;文献借阅、咨询服务、科技查新:66554700