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Corrosion behavior of SA508 low alloy steels exposed to aerated boric acid solutions

  • Lim, Yun Soo (Safety Materials Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Hwang, Seong Sik (Safety Materials Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Dong Jin (Safety Materials Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Lee, Jong Yeon (Safety Materials Technology Development Division, Korea Atomic Energy Research Institute)
  • Received : 2019.07.21
  • Accepted : 2019.11.26
  • Published : 2020.06.25

Abstract

The corrosion rates of the reactor pressure vessel materials of SA508 Grade 3 were measured using a weight loss method in aerated boric acid solutions to simulate the evaporation of leaked PWR primary water in an ambient environment. The corrosion behavior and products were examined using X-ray diffraction and electron microscopy. SA508 showed typical general corrosion characteristics. The corrosion rate increased steadily as the boron concentration was increased. As the immersion time elapsed, the corrosion rate slowly or rapidly decreased according to the oxidation reaction of iron. The corrosion rate showed a complicated pattern depending on the temperature; it increased gradually and then rapidly decreased again when reaching a certain transition temperature. The corrosion products of SA508 were found to be FeO(OH), Fe2O3, and Fe3O4. As the boron concentration decreased and the temperature was increased, the formation of Fe3O4 was more favorable as compared to the formation of FeO(OH) and Fe2O3. Consequently, the changes of the corrosion rate and behavior were closely related to the oxidation reaction of iron on the surface. The corrosive damage to SA508 appears to be most severe when the oxidation reaction is such that Fe2O3 forms as a corrosion product.

Keywords

References

  1. F. Cattant, Materials Ageing in Light Water Reactors: Handbook of Destructive Assays, Materials Ageing Institute, 2014, pp. 661-693.
  2. M. Le Calvar, I. De Curieres, Corrosion issues in pressurized water reactor (PWR) systems, in: Nuclear Corrosion Science and Engineering, Woodhead Pub. Series in Energy, 2012, pp. 473-547.
  3. H. Xu, S. Fyfitch, J.W. Hyres, Laboratory investigation of PWSCC of CRDM Nozzle 3 and its J-groove weld on the Davis-Besse reactor vessel head, in: Proc. Of the 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, 2005, pp. 833-842.
  4. H. Xu, S. Fyfitch, J.W. Hyres, Laboratory investigation of the stainless steel cladding on the Davis-Besse reactor vessel head, in: Proc. Of the 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, 2005, pp. 855-862.
  5. H. Xu, S. Fyfitch, J.W. Hyres, Boric acid corrosion laboratory investigation of the Davis-Besse reactor pressure vessel head, in: Proc. Of the 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, 2005, pp. 821-831.
  6. D. Lister, P. Phromwong, Boric-acid corrosion of carbon steel below perforated stainless steel cladding, in: Proc. Of the 17th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, 2015.
  7. P. Cohen, Water Coolant Technology of Power Reactors, Gordon and Breach Science Publishers, New York, 1969, pp. 220-231.
  8. J.H. Park, O.K. Chopra, K. Natesan, W.J. Shack, Boric acid corrosion of light water reactor pressure vessel materials, in: Proc. Of the 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, 2005, pp. 459-468.
  9. Q. Xiao, Z. Lu, J. Chen, M. Yao, Z. Chen, The effects of temperature and aeration on the corrosion of A508III low alloy steel in boric acid solutions at $25-95^{\circ}C$, J. Nucl. Mater. 480 (2016) 88-99. https://doi.org/10.1016/j.jnucmat.2016.08.009
  10. S. Fyfitch, H. Xu, Boric acid corrosion laboratory investigation of carbon and low-alloy steels in PWR Systems, in: 13th Int. Conf. On Environmental Degradation of Materials in Nuclear Power Systems, 2007.
  11. C.A. Campbell, S. Fyfitch, D.T. Martin, Boric Acid Corrosion of Carbon and Low Alloy Steels, NACE International, 1994. Corrosion 94, Paper 166.
  12. G.A. White, R.E. Jones, J.A. Gorman, C.R. Marks, J.E. Collin, R. Reid, Revision 2 of the EPRI boric acid corrosion guidebook, in: Proc. Of the 16th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, 2013.
  13. S.-W. Kim, D.-J. Kim, H.-P. Kim, Evaluation of galvanic corrosion behavior of SA-508 low alloy steel and type 309L stainless steel cladding of reactor pressure vessel under simulated primary water environment, Nucl. Eng. Technol. 44 (2012) 773-780. https://doi.org/10.5516/NET.07.2011.054
  14. ASTM Standard G1-03 (Reapproved 2011), Standard Practice for Preparing, Cleaning, and Evaluating Corrosion Test Specimens, ASTM International, 2001.
  15. ASME Boiler & Pressure Vessel Code Section II Part A SA508. Specification for Quenched and Tempered Vacuum-Treated Carbon and Alloy Steel Forgings for Pressure Vessels, ASME, 2007.
  16. M.-C. Kim, S.-G. Park, K.-H. Lee, B.-S. Lee, Comparison of fracture properties in SA508 Gr.3 and Gr.4N high strength low alloy steels for advanced pressure vessel materials, Int. J. Press. Vessel. Pip. 131 (2015) 60-66. https://doi.org/10.1016/j.ijpvp.2015.04.010
  17. K.-H. Lee, M.J. Jhung, M.-C. Kim, B.S. Lee, Effects of tempering and PWHT on microstructures and mechanical properties of SA508 Gr.4N steel, Nucl. Eng. Technol. 46 (2014) 414-422.
  18. NUREG/CR-2827, Boric Acid Corrosion of Ferritic Reactor Components, Nuclear Regulatory Commission, Washington, DC, July 1982.
  19. A.S. O'Neill, J.F. Hall, Boric Acid Corrosion of Carbon and Low-Alloy Steels Pressure-Boundary Components, EPRI NP-5985, Electric Power Research Institute, Palo Alto, CA, August 1988.
  20. D.A. Jones, Principles and Prevention of Corrosion, Macmillan Pub. Co., New York, 1992, pp. 9-24.