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划伤690TT合金在高温含氧水中应力腐蚀裂纹萌生的研究 |
孟凡江1,2, 王俭秋2, 韩恩厚2, 柯伟2 |
1. 上海核工程研究设计院 上海 200233; 2. 中国科学院金属研究所 沈阳 110016 |
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Stress Corrosion Crack Initiation for Scratched Alloy 690TT in Oxygenated High Temperature Water |
MENG Fanjiang1, WANG Jianqiu2, HAN En-Hou2, KE Wei2 |
1. Shanghai Nuclear Engineering Research and Design Institute,Shanghai,200233,China; 2. Institute of Metal Research,Chinese Academy of Sciences,Shenyang,110016,China |
引用本文:
孟凡江, 王俭秋, 韩恩厚, 柯伟. 划伤690TT合金在高温含氧水中应力腐蚀裂纹萌生的研究[J]. 中国腐蚀与防护学报, 2013, 33(5): 413-418.
MENG Fanjiang,
WANG Jianqiu,
HAN En-Hou,
KE Wei.
Stress Corrosion Crack Initiation for Scratched Alloy 690TT in Oxygenated High Temperature Water. Journal of Chinese Society for Corrosion and protection, 2013, 33(5): 413-418.
链接本文:
https://www.jcscp.org/CN/
或
https://www.jcscp.org/CN/Y2013/V33/I5/413
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[1] International Status and Prospects for Nuclear Power 2012. Board of Governors General Conference, IAEA. GOV/INF/2012/12-GC(56)/INF/6, 2012 [2] MacDonald P E, Shah V N, Ward L W, et al. Steam generator tube failures [R]. NUREG/CR-6365, 1996 [3] EPRI Report: TR-106863. Oconee 2 steam generator tube examination, 1997 [4] EPRI Report: TR-106484. Analysis of steam generator tubing from Oconee unit 1 nuclear station, 1997 [5] Staehle R W, Gorman J A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: part 1 [J]. Corrosion, 2003, 59: 931-994 [6] Staehle R W, Gorman J A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: part 3 [J]. Corrosion, 2004, 60: 115-180 [7] Meng F J, Wang J Q, Han E H, et al. Effects of scratching on corrosion and stress corrosion cracking of Alloy 690TT at 58 ℃ and 330 ℃ [J]. Corros. Sci., 2009, 51: 2761-2769 [8] Meng F J, Han E H, Wang J Q, et al. Localized corrosion behavior of scratches on nickel-base Alloy 690TT [J]. Electrochim. Acta, 2011, 56: 1781-1785 [9] Meng F J, Wang J Q, Han E H, et al. Microstructure near scratch on Alloy 690TT and stress corrosion induced by scratching [J]. Acta Metall. Sin., 2011, 47: 839-846 (孟凡江, 王俭秋, 韩恩厚等. 690TT合金划痕显微组织及划伤诱发的应力腐蚀 [J]. 金属学报, 2011, 47: 839-846) [10] Andresen P L, Morra M M, Ahluwalia A, et al. Effect of deformation and orientation on SCC of Alloy 690 [A]. The 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors [C]: Virginia Beach: August 23-27, 2009 [11] Lu Z P, Shoji T, Meng F J, et al. Effects of water chemistry and loading conditions on stress corrosion cracking of cold-rolled 316NG stainless steel in high temperature water [J]. Corros. Sci., 2011, 53: 247-262 [12] Yamazaki S, Lu Z, Ito Y, et al. The effect of prior deformation on stress corrosion cracking growth rates of Alloy 600 materials in a simulated pressurized water reactor primary water [J]. Corros. Sci., 2008, 50: 835-846 [13] EPRI Report: TR-105714-V2R4. PWR primary water chemistry guidelines, 1999 [14] Taunier S, Varry P, Tigeras A, et al. New primary shutdown and startup chemistry guidelines recently developed for EDF PWRs [A]. Proc. Int. Conf. Water Chem. Nuclear Reactors Syst. [C]. Berlin, 2008: L06-4 [15] Zhang Z M, Wang J Q, Han E H, et al. Influence of dissolved oxygen on oxide films of Alloy 690TT with different surface status in simulated primary water [J]. Corros. Sci., 2011, 53: 3623-3635 [16] Dan T C, Lv Z P, Wang J Q, et al. Crack growth behavior for stress corrosion cracking of 690 Alloy in high temperature water [J]. Acta Metall. Sin., 2010, 46: 1267-1274 (但体纯, 吕战鹏, 王俭秋等. 690合金在高温水中的应力腐蚀裂纹扩展行为 [J]. 金属学报, 2010, 46: 1267-1274) |
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