Environmentally assisted cracking in the low pressure superheated hydrogen steam

1. T. Couvant, L. Legras, A. Herbelin, A. Musienko, G. Ilevbare, D. Delafosse, G. Cailletaud, J. Hickling, Development of Understanding of The Interaction between Localized deformation and SCC of Austenitic Stainless Steels Exposed to Primary Environment, 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors 2010, 182–194. Search in Google Scholar

2. A. Herbelin, T. Couvant, L. Legras, D. Delafosse, G. Ilevbare, Oxidation of austenitic stainless steels in PWR primary water, EUROCORR 2009, 1592–1608. Search in Google Scholar

3. G. Economy, R. J. Jacko, F. W. Pement, IGSCC Behavior of Alloy 600 Steam-Generator Tubing in Water or Steam Tests above 360 C, Corrosion 1987, 43 (12), 727–73.10.5006/1.3583859 Search in Google Scholar

4. B. M. Capell, G. S. Was, Selective Internal Oxidation as a Mechanism of Intergranular Stress Corrosion cracking of Ni-Cr-Fe alloys, Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science 2007, 38 (6), 1244–1259.10.1007/s11661-007-9124-7 Search in Google Scholar

5. L. Chang, M. G. Burke, F. Scenini, Stress corrosion crack initiation in machined type 316L austenitic stainless steel in simulated pressurized water reactor primary water, Corrosion Science 2018, 138, 54–65.10.1016/j.corsci.2018.04.003 Search in Google Scholar

6. A. Hojná, M. Zimina, L. Rozumová, Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water, Journal of Nuclear Engineering and Radiation Science 2019, 5, DOI: 10.1115/1.404309910.1115/1.4043099 Search in Google Scholar

7. P. Pedeferri, Corrosion Science and Engineering, Springer 2018.10.1007/978-3-319-97625-9 Search in Google Scholar

8. U. Ehrnsten, Comprehensive Nuclear Materials, 5.05 Corrosion and Stress Corrosion Cracking of Austenitic Stainless Steels, Elsevier 2012, 93-103.10.1016/B978-0-08-056033-5.00080-X Search in Google Scholar

9. S. M. Bruemmer, E. P. Simonen, P. M. Scott, P. L. Andresen, J. L. Nelson, Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals, Journal of Nuclear Materials 1999, 274, 299-314.10.1016/S0022-3115(99)00075-6 Search in Google Scholar

10. D. Du, K. Chen, H. Lu, L. Zhang, X. Shi, X. Xu, P. L. Andresen, Effects of chloride and oxygen on stress corrosion cracking of coldworked 316/316L austenitic stainless steel in high temperature water, Corrosion Science 2016, 110, 134–142.10.1016/j.corsci.2016.04.035 Search in Google Scholar

11. S. Yamazaki, Z. Lu, Y. Ito, Y. Takeda, T. Shoji, The effect of prior deformation on stress corrosion cracking growth rates of Alloy 600 materials in a simulated pressurized water reactor primary water, Corrosion Science 2008, 50, 835–846.10.1016/j.corsci.2007.07.012 Search in Google Scholar

12. W. D. Callister, D. G. Rethwisch, Materials Science and Engineering, Wiley Binder Version 2014, ISBN: 978-1-118-47770-0. Search in Google Scholar

13. D. Du, K. Chen, L. Yu, H. lu, L. Zhang, X. Shi, X. Xu, SCC crack growth rate of cold worked 316L stainless steel in PWR environment, Journal of Nuclear Materials 2015, 456, 228–234.10.1016/j.jnucmat.2014.09.054 Search in Google Scholar

14. U S NRC Regulatory Guide 1.84, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III., U S NRC Regulatory Guide 1.85, 2005. Search in Google Scholar

15. D. Feron, Nuclear corrosion science and engineering, Woodhead 2012.10.1533/9780857095343 Search in Google Scholar

16. G. G. Scatigno, M. P. Ryan, F. Giuliani, M. R. Wenman, The effect of prior cold work on the chloride stress corrosion cracking of 304L austenitic stainless steel under atmospheric conditions. Materials Science and Engineering 2016, 668, 20–29.10.1016/j.msea.2016.05.037 Search in Google Scholar

17. A. Turnbull, K. Mingard, J. D. Lord, B. Roebuck, D. R. Tice, K. J. Mottershead, N. D. Fairweather, A. K. Bradbury, Sensitivity of stress corrosion cracking of stainless steel to surface machining and grinding procedure, Corrosion Science 2011, 53, 3398–3415.10.1016/j.corsci.2011.06.020 Search in Google Scholar

18. T. Couvant, L. Legras, A. Herbelin, A. Musienko, G. Ilevbare, D. Delafosse, G. Cailletaud, J. Hickling, Development of Understanding of the Interaction between Localized Deformation and SCC of Austenitic Stainless Steels Exposed to Primary PWR Environment, 14^th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems, 2009. Search in Google Scholar

19. S. Y. Persaud, A. Korinek, J. Huang, G. A. Botton, R. C. Newman, Internal oxidation of Alloy 600 exposed to hydro- genated steam and the beneficial effects of thermal treatment, Corrosion Science 2014, 86, 108–122.10.1016/j.corsci.2014.04.041 Search in Google Scholar

20. R-W. Bosch, S. Ritter, M. Herbst, R. Kilian, M. G. Burke, J. Duff, F. Scenini, Y. Gu, A. Dinu, U. Ehrnstén, A. Toivonen, R. Novotny, O. Martin, F-J Perosanz, A. Legat, B. Zajec, Stress corrosion crack initiation testing with tapered specimens in high-temperature water – results of a collaborative research project, Corrosion Engineering, Science and Technology 2020, DOI: 10.1080/1478422X.2020.1815460.10.1080/1478422X.2020.1815460 Search in Google Scholar

21. F. Scenini, R. C. Newman, R. A. Cottis, R. J. Jacko, Alloy 600 oxidation studies related to PWSCC, 12th International Symposium on Environmental Degradation of Materials in Nuclear Power System - Water Reactors 2005, 891–902. Search in Google Scholar

22. S.Y. Persaud, S. Ramamurthy, R.C. Newman, Internal oxidation of alloy 690 in hydrogenated steam, Corrosion Science 2015, 90, 606–613.10.1016/j.corsci.2014.11.006 Search in Google Scholar

23. S.Y. Persaud, S. Ramamurthy, A. Korinek, G.A. Botton, R.C. Newman, The influence of the high Fe and Cr contents of Alloy 800 on its inter-and intragranular oxidation tendency in 480 °C hydrogenated steam, Corrosion Science 2016, 106, 117–126.10.1016/j.corsci.2016.01.031 Search in Google Scholar

24. J. Janoušek, F. Scenini, L. Volpe, A. Hojná, T. Trojan, Instrumentation for SCC testing in low pressure superheated hydrogen steam environments, IOP Conference Series: Materials Science and Engineering 2018, 461 (1).10.1088/1757-899X/461/1/012031 Search in Google Scholar

25. L. Volpe, G. Bertali, M. Curioni, M. G. Burke, F. Scenini, Replicating PWR primary water conditions in low pressure H2-steam environment to study alloy 600 oxidation processes, Journal of The Electrochemical Society 2019, 166 (2), C1-C8.10.1149/2.0081902jes Search in Google Scholar

26. J. Janoušek, F. Scenini, L. Volpe, A. Hojná, M. G. Burke, Environmentally-assisted cracking of type 316L austenitic stainless steel in low pressure hydrogen steam environments, Procedia Structural Integrity 2019, 17, 440–447.10.1016/j.prostr.2019.08.058 Search in Google Scholar

27. A. Hojná, P. Halodova, J. Janoušek, M. Zimina, Acceleration of environmentally-assisted cracking initiation of the Type 316L steel in high temperature water and hydrogenated steam vapor environments, CORROSION 2020, 10.5006/3653.10.5006/3653 Search in Google Scholar

28. K. Chen, J. Wang, Z. Shen, D. Du, X. Guo, B. Gong, J. Liu, L. Zhang, Comparison of the stress corrosion cracking growth behavior of cold worked Alloy 690 in subcritical and supercritical water, Journal of Nuclear Materials 2019, 520, 235-244.10.1016/j.jnucmat.2019.04.017 Search in Google Scholar

29. X.H. Chen, J. Lu, L. Lu, K. Lu, Tensile properties of a nanocrystalline 316L austenitic stainless steel, Scripta Materialia 2005, 52, 1039–1044.10.1016/j.scriptamat.2005.01.023 Search in Google Scholar