journal article·2025-06

XPS and TEM characterization of oxides formed in simulated primary water on steam generator tubes made of Ni based alloy

Nathan Ribière, Jérôme Esvan, Nathalie Engler, Daniel Brimbal, Milan Skocic, Éric Andrieu, Christine Blanc, Lydia Laffont

Corrosion Science· Volume 249
Publisher page

Abstract

No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.

Source: Not provided · Quality: missing

Research context

OpenAlex topics: High-Temperature Coating Behaviors · Metallurgical Processes and Thermodynamics · Hydrogen embrittlement and corrosion behaviors in metals

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (48)

Show source-provided references
1. Influence of the transient conditions on release of corrosion products and oxidation of alloy 690 tubes during pressurized water reactor restart after steam generators replacement10.1016/j.jnucmat.2020.152562 ↗
2. XPS and STM study of the growth and structure of passive films in high temperature water on a nickel-base alloy10.1016/j.electacta.2004.04.032 ↗
3. Corrosion mechanisms of Ni-base alloys in pressurized water reactor primary conditions10.4028/www.scientific.net/MSF.595-598.529 ↗
4. M. Clauzel, M. Guillodo, M. Foucault, N. Engler, F. Chahma, C. Brun, Correlation between Ni base alloys surface conditioning and cation release mitigation in primary coolant, in: Nucl. Power Plant Conf. 2010 NPC, Canadian Nuclear Society, Canada, 2010. 〈https://inis.iaea.org/search/46102393〉.
5. S.El Euch, Recherche d’une corrélation entre caractéristiques électrochimiques et relâchement en nickel de l’alliage 690 en milieu primaire d’un réacteur à eau pressurisée, PhD Thesis, Sorbonne University, 2019. 〈http://www.theses.fr/2019SORUS090〉.
6. F. CarretteRelachement des produits de corrosion des tubes en alliage 690 de generateur de vapeur du circuit primaire des reacteurs a eau pressurisee, PhD Thesis, INP Toulouse, 2002, 〈http://www.theses.fr/2002INPT014G〉.
7. S. Gardey, Etude de la corrosion generalisee des alliages 600, 690 et 800 en milieu primaire. Contribution a la comprehension des mecanismes., PhD Thesis, Paris 6, 1998. 〈http://www.theses.fr/1998PA066134〉.
8. Kinetics of corrosion products release from nickel-base alloys corroding in primary water conditions: a new modelling of release
9. A. Machet, Study of the initial stages of oxidation of stainless steels in high temperature water, PhD Thesis, Paris 6, 2004. 〈http://www.theses.fr/2004PA066212〉.
10. X-ray photoelectron studies of the aqueous oxidation of inconel-600 alloy10.1149/1.2129132 ↗
11. The mechanism of oxide film formation on Alloy 690 in oxygenated high temperature water10.1016/j.corsci.2011.07.038 ↗
12. Corrosion behavior for alloy 690 and Alloy 800 tubes in simulated primary water10.1016/j.corsci.2012.10.018 ↗
13. Kinetics of passivation of a nickel-base alloy in high temperature water
14. Corrosion behavior of NiCrFe Alloy 600 in high temperature, hydrogenated water10.1016/j.corsci.2005.01.006 ↗
15. Analysis and TEM examination of corrosion scales grown on alloy 690 exposed to pressurized water at 325 °C: corrosion scales on alloy 690 grown in pressurized water10.1002/sia.1269 ↗
16. Impact of the startup temperature and primary chemistry program on the oxidation and release of corrosion products from alloy 690 steam generator
17. XPS study of Ni-base alloys oxide films formed in primary conditions of pressurized water reactor10.1002/sia.5757 ↗
18. A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactor10.1016/j.jnucmat.2010.05.010 ↗
19. ToF-SIMS study of the behavior of thermally oxidized films formed on nickel-based 690 alloy in high-temperature water: ToF-SIMS study of a thermally oxide film in high-temperature water10.1002/sia.5060 ↗
20. Laser surface melting of nickel-based alloy reduces nickel release in the primary cooling system of a nuclear power plant10.1016/j.optlastec.2021.107401 ↗
21. Influence of oxide films on primary water stress corrosion cracking initiation of alloy 60010.1016/j.jnucmat.2005.10.002 ↗
22. Long-term trends in the corrosion state and surface properties of the stainless steel tubes of steam generators decontaminated chemically in VVER-type nuclear reactors10.1016/j.corsci.2009.08.007 ↗
23. Comprehensive investigation of the corrosion state of the heat exchanger tubes of steam generators. Part II. Chemical composition and structure of tube surfaces10.1016/j.jnucmat.2005.09.013 ↗
24. J. Chen, F. Lindberg, P. Svanberg, F. Ehrlén, L. Corneliussion, J. Hägg, B. Bengtsson, Oxide Films on Ageing Materials of Alloy 600MA and Stainless steel from PWR Units, in: Nucl. Power Plant Conf. 2023 NPC, Juan-les-Pins, France, 2023.
25. The mechanism and kinetics of corrosion product release from stainless steel in lithiated high temperature water10.1016/0010-938X(87)90068-0 ↗
26. Oxidation kinetics and mechanisms of Ni-base alloys in pressurised water reactor primary conditions: influence of subsurface defects10.1016/j.corsci.2011.07.024 ↗
27. The mechanism of high temperature aqueous corrosion of stainless steels10.1016/0010-938X(91)90125-9 ↗
28. Corrosion of nickel-base alloys in primary medium of pressurized water reactors: New insights on the oxide growth mechanisms and kinetic modelling10.1016/j.corsci.2015.09.001 ↗
29. Influence of steam generator surface state on corrosion and oxide formation
30. F. Hamdani, Improvement of the corrosion and oxidation resistance of Ni-based alloys by optimizing the chromium content, INSA Lyon, 2015. 〈https://theses.hal.science/tel-01247500〉.
31. A. Loucif, Caractérisation photoélectrochimique des oxydes formés sur alliages base nickel en milieu primaire des réacteurs à eau pressurisée, Université de Grenoble, 2012.
32. Analysis and TEM examinations of corrosion scales grown on alloy 690 exposed to PWR environment10.1179/mht.2003.067 ↗
33. Multi-scale characterization of the inner surface of as-received steam generator tubes and correlation with the Ni release in primary water10.1016/j.corsci.2023.111205 ↗
34. An XPS and TEM study of the composition and structure of native oxides on the inner surface of as-received Ni base alloy steam generator tubes10.1016/j.apsusc.2024.159514 ↗
35. RCC-M M4105, Regles de conception et de construction des materiels mécaniques des ilots nucleaires REP, AFCEN, 2018.
36. L. Gouton, Formation par traitement de surface par laser d’une couche de chromine sur un alliage base nickel pour limiter le relâchement des cations en circuit primaire., PhD Thesis, Ecole Nationale Supérieure d’Arts et Métiers - ENSAM, 2015.
37. High-resolution X-ray photoemission spectrum of the valence bands of gold10.1103/PhysRevB.5.4709 ↗
38. L. Rioja-Monllor, L. Lautrup, J. Frodigh, Influence of high pH on the Ni-release and Oxide film of Alloy 690 Steam Generator Tubes, in: Nucl. Power Plant Conf. 2023 NPC, Juan-les-Pins, France, 2023.
39. The structure dependence of grain boundary passivation of alloy 690 in high temperature water10.1016/j.actamat.2023.119368 ↗
40. 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 ↗
41. Characterization of oxide films formed on alloy 182 in simulated PWR primary water10.1016/j.jnucmat.2009.06.012 ↗
42. X-ray photoelectron spectroscopic studies of nickel-oxygen surfaces using oxygen and argon ion-bombardment10.1016/0039-6028(74)90281-7 ↗
43. Oxidation of alloy 600 and alloy 690: experimentally accelerated study in hydrogenated supercritical water10.1007/s11661-016-3897-5 ↗
44. An atom probe tomography study of internal oxidation processes in alloy 60010.1016/j.actamat.2016.02.054 ↗
45. High resolution analysis of oxidation in Ni-Fe-Cr alloys after exposure to 315 °C deaerated water with added hydrogen10.1016/j.corsci.2016.02.009 ↗
46. Taishan EPR commissioning: chemistry of the primary and secondary water circuits during hot functional tests
47. Combined XPS / TEM study of the chemical composition and structure of the passive film formed on additive manufactured 17-4PH stainless steel
48. The oxidation of alloy 690 in simulated pressurized water reactor primary water10.1016/j.corsci.2017.07.004 ↗