Kinetics of hydrogen permeation through a Ni-base alloy membrane exposed to primary medium of pressurized water reactors
Source abstract
Abstract
Abstract Hydrogen permeation kinetics through a Ni-base alloy exposed to simulated pressurized water reactors primary medium at 325 °C has been investigated. In situ measurements exhibit a strong decrease of H flux during the first 50 h of exposure; it has been related to the oxide scale growth at the alloy surface. A kinetic model has been proposed to describe this link. Comparing modelling and experimental results indicates that high H transient activities are generated at the alloy surface during the first hours of oxide scale growth, suggesting that H could play a role in stress corrosion cracking of Ni-base alloys.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals · Corrosion Behavior and Inhibition
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (45)
Show source-provided references
1. IGSCC behaviour of Alloy 600 steam generator tubing in water or steam tests above 360 °C10.5006/1.3583859 ↗
2. Effect of electrode potential on the hydrogen-induced IGSCC of Alloy 600 in an aqueous solution at 350°C10.5006/1.3583860 ↗
3. Critical analysis of Alloy 600 stress corrosion cracking mechanisms in primary water10.1007/BF02649089 ↗
4. Stress corrosion cracking of alloy 600 and alloy 690 in hydrogen/steam at 380°C10.1016/S0010-938X(97)86103-3 ↗
5. Formation kinetics and rupture strain of Ni-Cr-Fe alloy corrosion films formed in high-temperature water10.1007/s11661-001-0176-9 ↗
6. Influence of oxide films on primary water stress corrosion cracking initiation of alloy 60010.1016/j.jnucmat.2005.10.002 ↗
7. Stress corrosion cracking of stainless steels and nickel alloys in high-temperature water10.5006/1.3278457 ↗
8. Advanced TEM characterization of stress corrosion craking of Alloy 600 in pressurized water reactor primary water environment10.1016/j.jnucmat.2009.06.014 ↗
9. Effects of cold working path on strain concentration, grain boundary microstructure and stress corrosion craking in Alloy 60010.1016/j.corsci.2011.05.037 ↗
10. Environmental effects on PWSCC initiation and propagation in Alloy 600
11. Environmentally assisted crack growth in one-dimensionally cold worked Alloy 690TT in primary water10.1016/j.corsci.2011.12.031 ↗
12. Characterization of microstructure, local deformation and microchemistry in Alloy 600 heat-affected zone and stress corrosion cracking in high temperature water10.1016/j.corsci.2012.01.029 ↗
13. Effect of chemical composition on grain boundary microchemistry and stress corrosion cracking in Alloy 18210.1016/j.corsci.2012.10.012 ↗
14. Quantitative assessment of intergranular damage due to PWR primary water exposure in structural Ni-based alloys10.1016/j.corsci.2012.09.048 ↗
15. Internal oxidation of Alloy 600 exposed to hydrogenated steam and the beneficial effects of thermal treatment10.1016/j.corsci.2014.04.041 ↗
16. The mechanism of stress corrosion cracking of Alloy 600 in high temperature water10.1016/0010-938X(96)00183-7 ↗
17. A stress corrosion cracking mechanism based on surface mobility10.1016/0010-938X(87)90117-X ↗
18. 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 ↗
19. A coupled environment model for stress corrosion cracking in sensitized type 304 stainless steel in LWR environments10.1016/0010-938X(91)90063-U ↗
20. Oxidation-deformation interactions and effect of environment on the crack growth resistance of Ni-base superalloys
21. Mechanisms of environmentally enhanced deformation and intergranular cracking of Ni–16Cr–9Fe alloys
22. An overview of internal oxidation as a possible explanation of intergranular SCC of alloy 600 in PWRS
23. Hydrogen effects on PWRSCC mechanisms in monocrystalline and polycrystalline alloy 600
24. Degradation of grain boundary strength by oxidation in Alloy 600
25. Effects of cold working degrees on grain boundary characters and strain concentration at grain boundaries in Alloy 60010.1016/j.corsci.2010.11.022 ↗
26. An update on the influence of hydrogen on the PWSCC of alloy 600 in high temperature water, American Nuclear Society Inc., La Grange Park
27. Evidence that carbide precipitation produces hydrogen traps in Ni-17Cr-8Fe alloys10.1016/S1359-6462(96)00440-X ↗
28. The effect of hydrogen on the fracture toughness of alloy X-750 at elevated temperatures10.1016/S0022-3115(98)00888-5 ↗
29. The effect of strain on the trapping of hydrogen at grain-boundary carbides in Ni-Cr-Fe alloys10.1007/s11661-001-0268-6 ↗
30. The influence of dissolved hydrogen on nickel alloy SCC: a window to fundamental insight
31. Role of temperature and strain rate on the hydrogen-induced intergranular rupture in Alloy 60010.1007/s11661-004-0356-5 ↗
32. Effect of dissolved hydrogen on the electrochemical behaviour of Alloy 600 in simulated PWR primary water at 290 °C10.1016/j.corsci.2011.02.020 ↗
33. First-principles study of hydrogen diffusion mechanism in Cr2O310.1007/s11431-010-4112-3 ↗
34. Characterization of oxygen and hydrogen migration through oxide scales formed on nickel-base alloys in PWR primary medium conditions10.1016/j.ssi.2012.10.012 ↗
35. Diffusion coefficient of tritium in Ni-based alloy10.13182/FST02-A22717 ↗
36. Role of grain boundaries in the diffusion of hydrogen in nickel base alloy 600: study coupling thermal desorption mass spectroscopy with numerical simulation10.1016/j.ijhydene.2016.07.038 ↗
37. Mechanism of hydrogen absorption during the exposure of alloy 600-like single-crystals to PWR primary simulated media10.1016/j.jnucmat.2011.04.066 ↗
38. Oxidation kinetics and mechanisms of Ni-base alloys in pressurized water reactor primary conditions: influence of subsurface defects10.1016/j.corsci.2011.07.024 ↗
39. 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 ↗
40. 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 ↗
41. XPS study of Ni-base alloys oxide films formed in primary conditions of pressurized water reactor10.1002/sia.5757 ↗
42. Hydrogen absorption associated with the corrosion mechanism of 316L stainless steels in primary medium of pressurized water reactor (PWR)10.1016/j.corsci.2014.04.025 ↗
43. Relations between the concentrations of imperfections in crystalline solids10.1016/S0081-1947(08)60135-6 ↗
44. Sarrazin · 2008
45. Philibert · 1991