Environmental Effects on Electrochemical Behaviors of Materials of a Dissimilar Metal Weld Exposed to High Temperature Primary Water of PWR Nuclear Power Plants

Abstract:

The effects of environmental factors on the electrochemical behaviors of the materials 52M and 316L taken from a dissimilar metal weld exposed to high temperature primary water of pressurized water reactor (PWR) nuclear power plants were studied experimentally, mainly on the effects of impurities chloride and sulfate in water, temperature and dissolved oxygen on the polarization curves, in order to provide fundamental data for relevant research and development. The results showed that doping chloride and sulfate into the water caused the rise of the tendency to pitting and general corrosion tendencies of both materials. With the rise of temperature from 160 °C to 290 °C, the tendencies to corrosion in anodic condition increased. The rise of the dissolved oxygen led to the rises of both the corrosion potentials and also the tendencies to corrosion.

• Periodical: Advanced Materials Research (Volume 1088)
• Pages: 169-173
• DOI: https://doi.org/10.4028/www.scientific.net/AMR.1088.169
• Online since: February 2015
• Authors: Guang Fu Li*, Ke Wei Fang, Jun Xu
• Keywords: Dissimilar Metal Weld, Electrochemical Behaviors, Environmental Factors, Nuclear Power Plant, Polarization Curve, Primary Water

References

[1] S.J. Zinkle, G.S. Was. Materials challenges in nuclear energy, Acta Materials, 2013, 61: 735-758.

[2] A. Jenssen, K. Norrgard, J. Lagerstrom, G. Embring, D. R. Tice, Assessment of cracking in dissimilar metal welds, Proceedings of Tenth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Aug. 2001，Lake Tahoe, USA , NACE International (USA), CD-ROM.

[3] W. H. Bamford, J. Foster, K. R. Hsu, L. Tunon-Sanjur, A. McIlree, Alloy 182 weld crack growth and its impact on service-induced cracking in operating PWR plant piping, ibid.

[4] W.H. Bamford, N. A. Palm, Service experience with Alloy 600 and associated welds in operating PWRs, including repair activities and regulatory and Code actions, Proc. of Fifteenth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, USA: The Metallurgical Society, 2011: 1525-1536.

[5] D.J. Paraventi and W.C. Moshier, Interaction of microstructure, composition, and cold work on the stress corrosion cracking of alloy 82 weld metal, ibid: 1087-1101.

DOI: 10.1002/9781118456835.ch112

[6] D. Alley and D. Dunn, Current NRC perspectives concerning primary water stress corrosion cracking, ibid: 14-27.

[7] P L Andresen, M M Morra and K Ahluwalia. SCC of Alloy 690 and its Weld Metals, ibid: 161-176.

DOI: 10.1002/9781118456835.ch19

[8] B Alexandreanu, Y Yang, Y Chen, et al. The Stress Corrosion Cracking Behavior of Alloys 690 and 152 Weld in a PWR Environment, Proceedings of Fourteenth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. USA: American Nuclear Society, 2009: 239-250.

DOI: 10.1002/9781118456835.ch21

[9] Kewei FANG, Guanjun LI, Guangfu LI, Wu YANG, Maolong ZHANG,  Zhiyuan SUN, Microstructure and Properties of Dissimilar Metal Weld A50852M316L Used for Nuclear Power Plants, Key Engineering Materials, 2011, vol. 479, pp.40-47.

DOI: 10.4028/www.scientific.net/kem.479.40

[10] J. Congleton R.A. Berrisford, W. Yang, Stress corrosion cracking of sensitized Type 304 stainless steel in doped high-temperature water, Corrosion, 1995, 51(12): 901-910.

DOI: 10.5006/1.3293566