When Alloy 600 (a nickel-base Fe–Cr–Ni alloy used for pressurized water reactor steam-generator tubing and penetration weldments) is strained at a slow rate in simulated primary water (boric acid plus lithium hydroxide) at , intergranular stress corrosion cracking (IGSCC) is accompanied by short-lived fluctuations in corrosion potential and in the current between the straining specimen and a counter-electrode. The 2002 study that produced these observations left open what the transient signatures actually prove: which crack-initiation mechanism they implicate, how much of the transient charge is supplied by the electrochemical double layer at a freshly created bare surface, and whether such signatures can be separated from recirculation-pump background noise and turned into an indicator of crack initiation. These three sub-questions remain unresolved: the slip-dissolution versus hydrogen-assisted mechanism controversy persists in authoritative reviews through 2019–2024, the double-layer-capacitance hypothesis has received no follow-up quantitative treatment, and electrochemical-noise interpretation and its development into an in-situ initiation diagnostic are still under active development (most recently for 304 stainless steel, not Alloy 600).
Background
Alloy 600 is a solid-solution nickel-base alloy (approximately 72 Ni, 15–16 Cr, 8–10 Fe, wt.%) selected in the 1960s–70s for steam-generator tubing and for pressurized water reactor (PWR) vessel-head and bottom instrumentation penetrations because of its general corrosion resistance. In PWR primary coolant — water containing boric acid (a neutron poison) and lithium hydroxide (a pH-control agent), pressurized to suppress boiling, typically near –, and hydrogenated to a low oxygen potential — the alloy nevertheless suffers intergranular stress corrosion cracking (IGSCC), called primary-water stress corrosion cracking (PWSCC) in this environment. The standard laboratory reproduction method is the slow strain rate test (SSRT): a specimen is pulled to failure at a strain rate near in a recirculating autoclave, and cracking susceptibility is read from the ductility loss and the intergranular fraction of the fracture surface. Because a stress-corrosion crack advances by discrete events — film rupture at a crack tip, transient anodic dissolution of the bare metal, and repassivation by oxide-film growth — the electrochemical state of the straining specimen carries a time-varying signature: short current spikes and potential fluctuations, collectively called electrochemical transients or electrochemical noise (EN). Two classical mechanism families compete to explain PWSCC: slip-dissolution, in which crack advance is the metal dissolved anodically each time plastic slip ruptures the protective film before it repassivates, and hydrogen-assisted (hydrogen-embrittlement-type) cracking, in which cathodically produced hydrogen concentrated at the crack tip degrades grain-boundary cohesion. These mechanisms are hard to separate in post-test metallography, which motivated in-situ electrochemical monitoring: in the late 1980s hydrogen was shown to accelerate IGSCC of Alloy 600 at (Totsuka et al., 1987), and by 2000 potential spikes had been recorded under PWR conditions and attributed to crack initiation events (Van Nieuwenhove, 2000), while Watanabe and Kondo (2000) had characterized current and potential fluctuation behavior during IGSCC of sensitized stainless steels under SSRT. Watanabe, Kain and Kobayashi (2002) transplanted this transient-monitoring approach to Alloy 600 in borated and lithiated water at and reported two observations that frame the open problem: the electrochemical transients were to be used to deliberate between competing IGSCC mechanisms, and the observed transient behavior implicated the double-layer capacitance of the specimen — the charge stored at the electrode–electrolyte interface — as a reservoir that can sustain anodic dissolution current in a low-oxygen high-temperature solution whose cathodic (reduction) reactions, and hence its ability to balance anodic dissolution, are limited by the scarce oxidant (a cathodically limited solution). Whether such signatures can be made quantitative, separated from facility background noise, and established as an in-situ crack-initiation indicator remains the unresolved core of this problem; a 2022 successor study for 304 stainless steel in the same water chemistry demonstrates that the interpretation methodology is still under construction.
Problem Statement
For Alloy 600 strained at a slow, controlled rate in a slow strain rate test (SSRT) in simulated PWR primary water (borated and lithiated, , low-oxygen, hydrogenated chemistry) while the current between the specimen and a counter-electrode and the free corrosion potential (the specimen's electrode potential measured against a reference electrode under zero applied current) are monitored continuously: (1) determine, from the electrochemical transients accompanying film rupture and repassivation at crack initiation sites, which mechanism dominates intergranular crack initiation — slip-dissolution (anodic dissolution of bare grain-boundary metal followed by repassivation) or hydrogen-assisted cracking — and with what relative contribution, the two being as yet indistinguishable in post-test examination; (2) quantify the role of the double-layer capacitance in sustaining the transient anodic dissolution current on a newly created bare surface in a low-oxygen high-temperature solution whose cathodic (reduction) reactions are limited by the scarce oxidant, i.e. how much of the observed transient charge is capacitive (stored as interfacial charge) rather than faradaic (carried by charge-transfer dissolution reactions), including the relevant capacitance values and time constants and how these scale with surface condition and film composition; (3) establish whether current and potential transient signatures are separable from pump- and flow-induced background noise with overlapping time constants, and whether they can be turned into an indicator of crack initiation for Alloy 600 in this environment, with attention to the extrapolation from accelerated test chemistry to in-service PWR primary water. The three sub-questions (1)–(3) are jointly required: the problem is fully resolved only when all three have been answered.
References
- Yutaka Watanabe, Vivekanand Kain, Makoto Kobayashi (2002), 'Electrochemical Transients Observed during Slow Strain Rate Test of Alloy 600 in Borated and Lithiated High Temperature Water', JSME International Journal Series A 45(4), 476–480, DOI: 10.1299/jsmea.45.476, https://doi.org/10.1299/jsmea.45.476
- Y. Watanabe, T. Kondo (2000), 'Current and Potential Fluctuation Characteristics in Intergranular Stress Corrosion Cracking Processes of Stainless Steels', Corrosion 56(12), 1250–1255, DOI: 10.5006/1.3280513, https://doi.org/10.5006/1.3280513
- R. Van Nieuwenhove (2000), 'Electrochemical Noise Measurements Under Pressurized Water Reactor Conditions', Corrosion 56(2), 161–166, DOI: 10.5006/1.3280532, https://doi.org/10.5006/1.3280532
- N. Totsuka, E. Lunarska, G. Gragnolino, Z. Szklarska-Smialowska (1987), 'Effect of Hydrogen on the Intergranular Stress Corrosion Cracking of Alloy 600 in High Temperature Aqueous Environments', Corrosion 43(8), 505–514, DOI: 10.5006/1.3583894, https://doi.org/10.5006/1.3583894
- R. Bandy, D. Van Rooyen (1984), 'Stress Corrosion Cracking of Inconel Alloy 600 in High Temperature Water—An Update', Corrosion 40(8), 425–430, DOI: 10.5006/1.3593950, https://doi.org/10.5006/1.3593950
- R. Rios, T. Magnin, D. Noel, O. de Bouvier (1995), 'Critical analysis of alloy 600 stress corrosion cracking mechanisms in primary water', Metallurgical and Materials Transactions A 26(4), 925–939, DOI: 10.1007/BF02649089, https://doi.org/10.1007/BF02649089
- Zhen Zhang, Xinqiang Wu (2022), 'Interpreting electrochemical noise signal arising from stress corrosion cracking of 304 stainless steel in simulated PWR primary water environment by coupling acoustic emission', Journal of Materials Research and Technology 20, 3807–3817, DOI: 10.1016/j.jmrt.2022.08.129, https://doi.org/10.1016/j.jmrt.2022.08.129
- Rik-Wouter Bosch, Marc Vankeerberghen, Serguei Gavrilov, Steven Dyck (2017), 'Electrochemical noise generated during stress corrosion cracking in high-temperature water and its relationship to repassivation kinetics', chapter 3 in Corrosion Monitoring in Nuclear Systems: Research and Applications, CRC Press, pp. 32–45, ISBN 9781906540982, DOI: 10.1201/9781315140391-4, https://doi.org/10.1201/9781315140391-4
- Vivekanand Kain (2012), 'Corrosion-Resistant Materials', chapter in Functional Materials (Elsevier), pp. 507–547, DOI: 10.1016/B978-0-12-385142-0.00012-X, https://doi.org/10.1016/B978-0-12-385142-0.00012-X
- Peter Gründler, Andreas Kirbs, Lothar Dunsch (2009), 'Modern Thermoelectrochemistry', ChemPhysChem 10(11), 1722–1746, DOI: 10.1002/cphc.200900254, https://doi.org/10.1002/cphc.200900254
- Xiaohui Li, Panpan Wu, Xinhe Xu, Zhanpeng Lu, Tongming Cui (2023), 'Comparison of SCC Results by Different Test Methods for Alloy 600 in High Temperature Water', Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 2, pp. 1123–1130, DOI: 10.1007/978-981-19-8780-9_108, https://doi.org/10.1007/978-981-19-8780-9_108
- Peter M. Scott, Pierre Combrade (2019), 'General corrosion and stress corrosion cracking of Alloy 600 in light water reactor primary coolants', Journal of Nuclear Materials 524, 340–375, DOI: 10.1016/j.jnucmat.2019.04.023, https://doi.org/10.1016/j.jnucmat.2019.04.023
- P.L. Andresen (2016), 'Understanding and predicting stress corrosion cracking (SCC) in hot water', chapter in Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors, pp. 169–238, DOI: 10.1016/B978-0-08-100049-6.00005-7, https://doi.org/10.1016/B978-0-08-100049-6.00005-7
- D.D. Macdonald (2016), 'The electrochemical nature of stress corrosion cracking', chapter in Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors, pp. 239–294, DOI: 10.1016/B978-0-08-100049-6.00006-9, https://doi.org/10.1016/B978-0-08-100049-6.00006-9
- Pan Liu, Yunlong Wu, Xiangyu Zhong, Ken Oyama, Seiya Ogota, Jun Chai, Yutaka Watanabe, Tetsuo Shoji (2024), 'New insights into stress corrosion cracking mechanism of Alloy 600 in boiling water reactor (BWR) environment', Corrosion Science 232, 112008, DOI: 10.1016/j.corsci.2024.112008, https://doi.org/10.1016/j.corsci.2024.112008
- Yutaka Watanabe, Vivekanand Kain, Makoto Kobayashi (2001), 'Electrochemical Transients Observed during Slow Strain Rate Test of Alloy 600 in Borated and Lithiated High Temperature Water', Proceedings of the Asian Pacific Conference on Fracture and Strength and International Conference on Advanced Technology in Experimental Mechanics (APCFS & ATEM 2001), 120–125, DOI: 10.1299/jsmeatemapcfs.1.01.203.0_120, https://doi.org/10.1299/jsmeatemapcfs.1.01.203.0_120