Stress corrosion crack initiation in filler metal 82 in oxygenated high-temperature water
Source abstract
Abstract
The Stress Corrosion Cracking (SCC) initiation in filler metal (FM) 82 was studied in oxygenated (O2) water at 288 °C. Post-test microstructural characterization revealed that cracked grain boundaries (GBs) always exhibited a porous oxide incursion. Some intergranular (IG) cracks exhibited an oxide along the crack walls, which appeared to form after the crack advanced. Furthermore, similar porous oxide incursions were observed at the GBs on the non-stressed FM 82 coupon after oxidizing for a similar duration. The formation of oxide incursions is discussed, and the evolution of crack initiation is proposed.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Corrosion Behavior and Inhibition · High-Temperature Coating Behaviors
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (61)
Show source-provided references
1. Film-rupture mechanism of stress corrosion10.6028/jres.048.013 ↗
2. Role of slip step emergence in the early stages of stress corrosion cracking in face centered iron-nickel-chromium alloys10.5006/0010-9312-23.5.117 ↗
3. Life prediction by mechanistic modeling and system monitoring of environmental cracking of iron and nickel alloys in aqueous systems10.1016/0025-5416(88)90564-2 ↗
4. P.L. Andresen, R. Reid, J. Wilson, SCC mitigation of Ni alloys and weld metals by optimizing dissolved hydrogen, In: Proceedings of the 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2009: pp. 345–372.
5. P.L. Andresen, P.W. Emigh, M.M. Morra, Effect of PWR primary water chemistry and deaerated water on SCC, In: Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2005: pp. 989–1008.
6. 5 - Understanding and predicting stress corrosion cracking (SCC) in hot water
7. The mechanism of oxide film formation on Alloy 690 in oxygenated high temperature water10.1016/j.corsci.2011.07.038 ↗
8. Influence of dissolved oxygen concentration on the oxide film formed on Alloy 690 in high temperature water10.1016/j.corsci.2012.12.003 ↗
9. M. Maisonneuve, C. Guerre, C. Duhamel, J. Crépin, I. de Curières, Effect of Aerated Transients on Oxidation and SCC of Stainless Steels in PWR Primary Water, In: Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2019: pp. 986–1000.
10. Microstructural causes of intergranular corrosion of alloys 82 and 182.10.5006/1.3583898 ↗
11. J.M. Boursier, F. Vaillant, B. Yrieix, Weldability, Thermal Aging and PWSCC Behavior of Nickel Weld Metals Containing 15 to 30% Chromium, In: Proceedings of the ASME/JSME 2004 Pressure Vessels and Piping Conference, 2004: pp. 109–121.10.1115/PVP2004-3061 ↗
12. J. Daret, Etude paramétrique et statistique de la sensibilité à la fissuration par corrosion sous contrainte d′alliages base nickel déposés – Bilan des essais menés en boucles CASTOR, POLLUX et VENUS, Technical Reports SCECF 526. 526 (2003).
13. S. Le Hong, Caractérisation métallurgique et résistance à la corrosion sous contrainte des alliages 182 et 82 en milieu primaire des REP. Synthèse des connaissances en 98, Technical Report EDF HT-44/97/014/B. (1998).
14. F. Vaillant, J.M. Boursier, L. Legras, B. Yrieix, E. Lemaire, J. Champredonde, C. Amzallag, A review of weldability and SCC behaviors of Ni-base weld metals in laboratory PWR environment, In: Proceedings of the 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2007.
15. S. Le Hong, F. Vaillant, C. Amzallag, Synthesis and comparison of crack growth rate measurements on tubes and plates in Alloy 600 in high temperature hydrogenated primary water, In: Proceedings of EUROMAT, 2000.
16. E. Chaumun, J. Crépin, I. De Curières, C. Duhamel, C. Guerre, E. Héripré, M. Sennour, Initiation of SCC crack in nickel based weld metals: influence of microstructure features, in: 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2013.
17. Y. Sakakibara, G. Nakayama, T. Hirano, Effect of plastic strain on the susceptibility to stress corrosion cracking for nickel-base alloys in simulated BWR environment, In: Proceedings of the 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2013.
18. Effect of chromium content on stress corrosion cracking susceptibility of shielded metal arc weld metals for 600 type alloy in high-temperature pressurised pure water10.1080/09507116.2012.708499 ↗
19. G.A. Young, R.A. Etien, M.J. Hackett, J.D. Tucker, T.E. Capobianco, Physical metallurgy, weldability, and in-service performance of nickel-chromium filler metals used in nuclear power systems, In: Proceedings of the 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2009.
20. W.J. Mills, C.M. Brown, M.G. Burke, Effect of microstructure on low temperature cracking behavior of EN82H welds, In: Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2001.
21. J. Kaneda, T. Horiuchi, J. Kuniya, H. Nagase, M. Koshiishi, Investigation of precipitation and segregation on grain boundaries in Ni-Based alloys and welds, In: Proceedings of the 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2007.
22. P.M. Scott, M. Le Calvar, Some possible mechanisms of intergranular stress corrosion cracking of Alloy 600 in PWR primary water, In: Proceedings of the 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), San Diego, California, USA, 1993: pp. 657–667.
23. Advanced microstructural characterization of the intergranular oxidation of Alloy 60010.1016/j.corsci.2015.08.010 ↗
24. Bertali · 2016
25. D. Gómez-Briceño, J. Lapeña, M.S. García, L. Castro, F. Perosanz, K. Ahluwalia, J. Hickling, IGSCC initiation from weld defects in alloy 600/82, In: Proceedings of the 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2009: pp. 422–434.
26. Alexandreanu · 2002
27. Characterization of oxide scales formed on alloy 82 in nominal PWR primary water at 340 °C and in hydrogenated steam at 400 °C10.1016/j.corsci.2017.11.029 ↗
28. Oxidation of nickel-base welds 182 and 82 in simulated primary water of pressurised water reactors10.1179/1878641314Y.0000000031 ↗
29. The effect of weld chemistry on the oxidation of Alloy 82 dissimilar metal welds10.1016/j.corsci.2014.10.044 ↗
30. Stress corrosion cracking initiation and short crack growth behaviour in Alloy 182 weld metal under simulated boiling water reactor hydrogen water chemistry conditions10.1016/j.corsci.2017.11.021 ↗
31. Accelerated test for evaluation of intergranular stress corrosion cracking initiation characteristics of non-sensitized 316 austenitic stainless steel in simulated pressure water reactor environment
32. Effects of surface treatments on environmentally-assisted cracking susceptibility of Alloy 182 in BWR environment10.1016/j.corsci.2021.109555 ↗
33. Investigation of surface treatment effects on the environmentally-assisted cracking behaviour of Alloy 182 in boiling water reactor environment10.1080/1478422X.2022.2083746 ↗
34. Stress corrosion crack initiation in machined type 316L austenitic stainless steel in simulated pressurized water reactor primary water10.1016/j.corsci.2018.04.003 ↗
35. Effects of hydrogen on stress corrosion crack growth rate of nickel alloys in high-temperature water10.5006/1.3278508 ↗
36. P.L. Andresen, SCC of controlled chemistry alloy 182 and 82 weld metals in BWR water, In: Proceedings of the 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2009: pp. 382–408.10.5006/C2010-10284 ↗
37. High temperature behavior of Ni-base weld metal: Part II. Insight into the mechanism for ductility dip cracking.
38. The mechanism of high temperature aqueous corrosion of stainless steels10.1016/0010-938X(91)90125-9 ↗
39. The mechanism and kinetics of corrosion product release from stainless steel in lithiated high temperature water10.1016/0010-938X(87)90068-0 ↗
40. The mechanism of oxide film formation on austenitic stainless steels in high temperature water10.1016/S0010-938X(97)00140-6 ↗
41. Effect of phosphate ions on the formation of iron oxide/hydroxide as a stabilizer10.1016/j.jssc.2021.122688 ↗
42. The role of TiN inclusions in stress corrosion crack initiation for Alloy 690TT in high-temperature and high-pressure water10.1016/j.corsci.2009.11.015 ↗
43. Analysis of oxide film formed on type 304 stainless steel in 288°C water containing oxygen, hydrogen, and hydrogen peroxide10.5006/1.3283969 ↗
44. Characterization of the oxide film formed on type 316 stainless steel in 288°C water in cyclic normal and hydrogen water chemistries10.5006/1.3293562 ↗
45. Influence of dissolved hydrogen on structure of oxide film on Alloy 600 formed in primary water of pressurized water reactors10.1080/18811248.2003.9715385 ↗
46. Effect of hydrogen in Inconel Alloy 600 on corrosion in high temperature oxygenated water10.1016/j.corsci.2009.11.037 ↗
47. Corrosion behavior of 304 stainless steel in high temperature, hydrogenated water10.1016/S0010-938X(02)00004-5 ↗
48. Microstructural characteristics of the oxide scale formed on 304 stainless steel in oxygenated high temperature water10.1016/j.corsci.2010.07.015 ↗
49. N. Supornpaibul, M.G. Burke, J. Duff, F. Scenini, Y. Wang, Understanding the effect of water chemistry and surface grinding on the stress corrosion cracking initiation of filler metal, 82, In: Proceedings of the 20th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, 2022.10.1016/j.corsci.2023.111008 ↗
50. Corrosion behavior of alloys 625 and 718 in supercritical water10.5006/1.3278410 ↗
51. Corrosion behavior of Ni-base alloys for advanced high temperature water-cooled nuclear plants10.1016/j.corsci.2008.08.024 ↗
52. Corrosion behavior of Alloy 690 in aerated supercritical water10.1016/j.corsci.2012.10.001 ↗
53. A comparative study of oxide scales grown on stainless steel and nickel-based superalloys in ultra-high temperature supercritical water at 800 °C10.1016/j.corsci.2016.02.004 ↗
54. The effect of residual stress on the preferential intergranular oxidation of alloy 60010.1016/j.corsci.2016.05.022 ↗
55. The effect of temperature on the preferential intergranular oxidation susceptibility of alloy 60010.1007/s11661-018-4491-9 ↗
56. Internal oxidation of Alloy 600 exposed to hydrogenated steam and the beneficial effects of thermal treatment10.1016/j.corsci.2014.04.041 ↗
57. Grain boundary depletion and migration during selective oxidation of Cr in a Ni–5Cr binary alloy exposed to high-temperature hydrogenated water10.1016/j.scriptamat.2014.06.022 ↗
58. T. Moss, M.J. Olszta, W. Grant, G.S. Was, Grain boundary oxidation and stress corrosion cracking in nickel-base alloys strained in supercritical water, In: Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, The Minerals, Metals and Materials Society (TMS), 2015.
59. Understanding the role of diffusion induced grain boundary migration on the preferential intergranular oxidation behaviour of alloy 600 via advanced microstructural characterization10.1016/j.actamat.2019.06.021 ↗
60. Characterization of initial intergranular oxidation processes in alloy 600 at a sub-nanometer scale10.1016/j.corsci.2018.01.020 ↗
61. Effects of boundary migration and pinning particles on intergranular oxidation revealed by 2D and 3D analytical electron microscopy10.1016/j.actamat.2017.04.003 ↗