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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 |
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Abstract The stress corrosion crack (SCC) initiation of Alloy 690TT was studied by using scratch technique in oxygenated water at 325 ℃. The SEM results show that intergranular stress corrosion cracks were initiated at the bottom of the scratch groove,and the relevant mechanism was discussed. Mechanical cracks which were produced during slow strain rate tensile stage and tips ofthem highly approached to or were along grain boundaries,could be the precursor for stress corrosion crack initiation and growth in the following constant loading stage. Therefore,Alloy 690TT is susceptible to stress corrosion cracking in high temperature oxygenated water.
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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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