Microstructure of Heat-Affected Zone in a Weld Joint between Alloy 690 and Alloy 152

被引：0
|
作者：
Nie S. [1 ]
Liang Z. [1 ]
机构：
[1] China Institute of Atomic Energy, Beijing
来源：
| 1600年 / Atomic Energy Press卷 / 38期
关键词：
Grain boundary microstructure; Heat-affected zone; Intra-grain average misorientation; Metallurgical characteristics; Residual strains;
D O I：
10.13832/j.jnpe.2017.04.0139
中图分类号：
学科分类号：
摘要：
The distributions of residual strains, micro-hardness, intra-grain average misorientation(GAM), grain boundary microstructure and metallurgical characteristics were investigated at the top, middle and root of the heat-affected zone of a weld joint between pressurized water reactor (PWR) control rod drive mechanism (CRDM) Nozzle Alloy 690 and Alloy 152 using electron backscatter diffraction (EBSD), scanning electron microscopy (SEM) and micro-hardness tester. The results showed that the residual strain decreased from the last welding top of the weld to root, the maximum residual strain is 5.15% at the top of the last weld; the average fraction of coincident site lattice ∑3 special boundaries increased from the last welding top of the weld to root, the minimum fraction of ∑3 special boundaries is 46.6%, which is remarkably less than that 68% of the base 690 alloy. The HAZ at the top of the weld is considered to sustain the highest stress corrosion cracking (SCC) susceptibility. © 2017, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.
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页码：139 / 144
页数：5
相关论文
共 13 条
  • [1] Scott P.M., Combrade P., On the mechanism of stress corrosion crack initiation and growth alloy 600 exposed to PWR primary water, 11th International Symposium on Environmental Degradation of Materials inNuclear Power Systems-Water Reactors, (2003)
  • [2] Hong S.L., Boursier J.M., Amzallag C., Measurement of stress corrosion growth rates in weld alloy 182 in primary water, 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (2001)
  • [3] Yamazaki S., Lu Z., The effect of prior deformation on stress corrosion cracking growth rates of Alloy 600 materials in a simulated PWR primary water, Corrosion science, 750, 3, pp. 835-846, (2008)
  • [4] Young G.A., Lewis N., The stress corrosion crack growth rate of Alloy 600 Heat affected zones exposed to high purity water, Prof. Conference on Vessel Head Penetration Inspection, (2003)
  • [5] Lee S.-H., Chang Y.-S., Residual stress assessment of nickel-base alloys 690 welding parts, Engineering Failure Analysis, 54, 1, pp. 57-73, (2015)
  • [6] Hou J., Shoji T., Lu Z.P., Residual strain measurement and grain boundary characterization in the heat affected zone of a weld Joint between Alloy 690TT and Alloy 52, Journal of Nuclear Materials, 397, 1, pp. 109-115, (2010)
  • [7] Lu B.T., Chen Z.K., Pitting and stress corrosion cracking behavior in welded austenitic stainless steel, ElectrochimicaActa, 50, 6, pp. 1391-1403, (2005)
  • [8] Crawford D.C., Was G.S., The role of grain boundary misorientation on the intergranular cracking behavior of Ni-16Cr-9Fe in 360℃ Argon and high purity water, Metall. Trans, A23, pp. 1195-1206, (1992)
  • [9] Pan Y., Adams B.L., Grain boundary structure effects on intergranular stress corrosion cracking of alloy X-750, Acta Metall. Materialia, 44, 1, pp. 4685-4695, (1996)
  • [10] Gertsman V.Y., Bruemmer S.M., Study of grain boundary character along intergranular stress corrosion crack paths in austenitic alloys, Acta Materialia, 49, 9, pp. 1589-1598, (2001)
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