Effects of He ion irradiation on the corrosion performance of alloy GH3535 welded joint in molten FLiNaK
Source abstract
Abstract
Abstract In present study, the influence of He irradiation on the corrosion performance of a GH3535 welded joint has been investigated. A welded joint was irradiated with 300 keV He ions and corroded in FLiNaK molten salt at 700 °C for 400 h. The microstructures after corrosion were characterized by SEM, EPMA and TEM. The corrosion produced cavities and created Cr depletion. He bubbles were formed and grew during corrosion. Although He irradiation did not obviously deteriorate corrosion-induced Cr depletion, the combination effect of He bubbles and corrosion attack caused severe damage to the joint, enlarging bubbles and/or cavities into large holes.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Nuclear reactor physics and engineering
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References (25)
Show source-provided references
1. P.N.H.M.W. Rosenthal, R.B. Briggs, The development status of mqltem-salt breeder reactors, ORNL-4812 (1972) 195-218.
2. Grain boundary engineering for control of tellurium diffusion in GH3535 alloy10.1016/j.jnucmat.2017.10.052 ↗
3. H.G. MocPherson, Molten salt reactor program quarterly progress report, ORNL-2626 (1958) 1-96.
4. Intergranular corrosion of welded joints of austenitic stainless steels studied by using an electrochemical minicell10.1016/j.corsci.2008.06.016 ↗
5. Effects of exposing duration on corrosion performance in weld joint of Ni-Mo-Cr alloy in FLiNaK molten salt10.1016/j.jfluchem.2016.07.007 ↗
6. Effects of exposing temperature on corrosion performance of weld joint of a Ni–Mo–Cr alloy10.1016/j.jfluchem.2015.12.005 ↗
7. Effects of SO42− ions on the corrosion of GH3535 weld joint in FLiNaK molten salt10.1016/j.jnucmat.2017.05.020 ↗
8. Perspectives on radiation effects in nickel-base alloys for applications in advanced reactors10.1016/j.jnucmat.2009.03.023 ↗
9. M. HE, Status of materials development for molten salt reactors, ORNL-TM-5920 (1978) 1-30.
10. Corrosion characteristics of Hastelloy N alloy after He+ ion irradiation10.1080/00223131.2014.854181 ↗
11. High-temperature corrosion of helium ion-irradiated Ni-based alloy in fluoride molten salt10.1016/j.corsci.2014.11.013 ↗
12. Effects of bubbles on high-temperature corrosion of helium ion-irradiated Ni-based alloy in fluoride molten salt10.1016/j.corsci.2017.06.027 ↗
13. Structural materials for Gen-IV nuclear reactors: challenges and opportunities10.1016/j.jnucmat.2008.08.044 ↗
14. H.E. McCoy Jr., Status of materials development for molten salt reactors, ORNL-TM-5920 (1978) 1-31.10.2172/5195742 ↗
15. SRIM—the stopping and range of ions in matter (2010)10.1016/j.nimb.2010.02.091 ↗
16. Microstructure of helium-implanted and proton-irradiated T91 ferritic/martensitic steel10.1016/j.jnucmat.2007.03.118 ↗
17. A special coarsening mechanism for intergranular helium bubbles upon heating: a combined experimental and numerical study10.1016/j.scriptamat.2018.01.006 ↗
18. Imaging of high-angle annular dark-field scanning transmission electron microscopy and observations of GaN-based violet laser diodes10.1111/j.1365-2818.2006.01613.x ↗
19. Materials corrosion in molten LiF–NaF–KF salt10.1016/j.jfluchem.2008.05.008 ↗
20. The high-temperature corrosion of Hastelloy N alloy (UNS N10003) in molten fluoride salts analysed by STXM, XAS, XRD, SEM, EPMA, TEM/EDS10.1016/j.corsci.2016.02.010 ↗
21. Influence of graphite-alloy interactions on corrosion of Ni-Mo-Cr alloy in molten fluorides10.1016/j.jnucmat.2018.03.001 ↗
22. Helium accumulation in metals during irradiation – where do we stand?10.1016/j.jnucmat.2003.09.001 ↗
23. Calculated size distributions for gas bubble migration and coalescence in solids10.1063/1.1708962 ↗
24. The role of fission gas re-solution during post-irradiation heat treatment10.1016/0022-3115(62)90104-6 ↗
25. Microstructural evolution and mechanical properties of 2D-SiCf/SiC and Hastelloy N joints using 82.5Au-17.5Ni brazing filler10.1002/adem.201600229 ↗