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Electrochemical Behavior of Platinum Treated Type 304 Stainless Steels in Simulated BWR Environments Under Startup Conditions

  • Chu-Yung Yuan
  • Tsung-Kuang Yeh
  • Mei-Ya WangEmail author
Conference paper
Part of the The Minerals, Metals & Materials Series book series (MMMS)

Abstract

As reactor startup begins, the ECP is initially high in the oxygenated water environment established during a cold shutdown. Consequently, the components would exhibit the higher crack initiation and propagation rates of IGSCC during startup period than in the remainder of the cycle. The corrosion current density response of stainless steel exposed to H2O2 was larger than that of those exposed to O2, and it remained at a higher value even at the low level of several ppb. As noble metal was applied in the BWRs to catalyze the chemical reactions of H2O2 and O2, this study evaluated the corrosion behaviors of both oxidants on the components of stainless steel. The corrosion potentials and corrosion current densities of 304SS with Pt coating were investigated in pure water with dissolved oxygen or hydrogen peroxide concentrations at various temperatures.

Keywords

Stress corrosion cracking Reactor startup 304 stainless steel Pt Normal water chemistry 

References

  1. 1.
    S. Hettiarachchi, BWR SCC Mitigation experiences with hydrogen water chemistry, in Proceedings of the 12th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, (TMS The Minerals, Metals & Materials Society, Salt Lake City, UT, U.S.A., August 14–18, 2005), pp. 685–699Google Scholar
  2. 2.
    R.L. Cowan, The mitigation of IGSCC of BWR internals with hydrogen water chemistry, in Water Chemistry of Nuclear Reactor Systems 7 (BNES, Bournemouth, England, 13–17 October 1996), p. 196Google Scholar
  3. 3.
    S.E. Garcia et al., Effect of hydrazine, carbohydrazide and hydrogen injection on noble metal treated stainless steel ECP and IGSCC mitigation during BWR startups, in 2010 International Conference on Water Chemistry of Nuclear Reactor Systems (Quebec City, Canada, 3–7 October 2010), 3.09PGoogle Scholar
  4. 4.
    A. Abe et al., Mitigation of SCC initiation on BWR core internals by means of hydrogen water chemistry during start-up. Nucl. Sci. Eng. 149, 312 (2005)CrossRefGoogle Scholar
  5. 5.
    K. Ishida et al., Applying hydrogen water chemistry to boiling water reactor during normal operation and start-up to mitigate stress corrosion cracking at shimane nuclear power station’s unit 2, in 2008 International Conference on Water Chemistry of Nuclear Reactor Systems (Berlin, Germany, 14–18 September 2008), L04-3Google Scholar
  6. 6.
    S.E. Garcia, A.D. Odell, J.F. Giannelli, Early hydrogen water chemistry in the boiling water reactor: industry-first demonstration, in 2012 International Conference on Water Chemistry of Nuclear Reactor Systems (Paris, France, 23–27 September 2012), P2-64-82Google Scholar

Copyright information

© The Minerals, Metals & Materials Society 2019

Authors and Affiliations

  1. 1.Department of Engineering and System ScienceNational Tsing Hua UniversityHsinchuTaiwan
  2. 2.Institute of Nuclear Engineering and ScienceNational Tsing Hua UniversityHsinchuTaiwan
  3. 3.Nuclear Science Technology and Development CenterNational Tsing Hua UniversityHsinchuTaiwan

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