journal article·2024-02-01Open access

Coupling of radiation and grain boundary corrosion in SiC

Jianqi Xi, Hongliang Zhang, Ranran Su, Shuguang Wei, Xuanxin Hu, Benoit Queylat, Taeho Kim, Adrien Couet, Izabela Szlufarska

npj Materials Degradation· Volume 8· Issue 1

Abstract

Abstract Radiation and corrosion can be coupled to each other in non-trivial ways and such coupling is of critical importance for the performance of materials in extreme environments. However, it has been rarely studied in ceramics and therefore it is not well understood to what extent these two phenomena are coupled and by what mechanisms. Here, we discover that radiation-induced chemical changes at grain boundaries of ceramics can have a significant (and positive) impact on the corrosion resistance of these materials. Specifically, we demonstrate using a combination of experimental and simulation studies that segregation of C to grain boundaries of silicon carbide leads to improved corrosion resistance. Our results imply that tunning of stoichiometry at grain boundaries either through the sample preparation process or via radiation-induced segregation can provide an effective method for suppressing surface corrosion.
Source: crossref · Quality: baseline

Research context

OpenAlex topics: Advanced ceramic materials synthesis · Nuclear materials and radiation effects · Fusion materials and technologies

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

References (35)

Show source-provided references
1. Was, G. S., Petti, D., Ukai, S. & Zinkle, S. Materials for future nuclear energy systems. J. Nucl. Mater. 527, 151837 (2019).10.1016/j.jnucmat.2019.151837 ↗
2. Bruemmer, S. M. et al. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals. J. Nucl. Mater. 274, 299–314 (1999).10.1016/S0022-3115(99)00075-6 ↗
3. Allen, T., Busby, J., Meyer, M. & Petti, D. Materials challenges for nuclear systems. Mater. Today 13, 14–23 (2010).10.1016/S1369-7021(10)70220-0 ↗
4. Zinkle, S. J. & Was, G. S. Materials challenges in nuclear energy. Acta Mater. 61, 735–758 (2013).10.1016/j.actamat.2012.11.004 ↗
5. Zhang, H. et al. The damage evolution of He irradiation on Ti3SiC2 as a function of annealing temperature. J. Eur. Ceram. Soc. 38, 1253–1264 (2018).10.1016/j.jeurceramsoc.2017.11.041 ↗
6. Lee, W. E., Gilbert, M., Murphy, S. T. & Grimes, R. W. Opportunities for advanced ceramics and composites in the nuclear sector. J. Am. Ceram. Soc. 96, 2005–2030 (2013).10.1111/jace.12406 ↗
7. Marra, J. Advanced ceramic materials for next-generation nuclear applications. IOP Conf. Ser. Mater. Sci. Eng. 18, 162001 (2011).10.1088/1757-899X/18/16/162001 ↗
8. Bongiorno, A. et al. A perspective on modeling materials in extreme environments: Oxidation of ultrahigh-temperature ceramics. MRS Bull. 31, 410–417 (2006).10.1557/mrs2006.103 ↗
9. Su, R. et al. Enhanced oxidation resistance of (Mo95W5)85Ta10(TiZr)5 refractory multi-principal element alloy up to 1300 °C. Acta Mater. 215, 117114 (2021).10.1016/j.actamat.2021.117114 ↗
10. Zhang, H. et al. Enhancing the phase stability of ceramics under radiation via multilayer engineering. Sci. Adv. 7, eabg7678 (2021).10.1126/sciadv.abg7678 ↗
11. Tan, L., Allen, T. R. & Busby, J. T. Grain boundary engineering for structure materials of nuclear reactors. J. Nucl. Mater. 441, 661–666 (2013).10.1016/j.jnucmat.2013.03.050 ↗
12. Asher, R. C., Davies, D., Kirstein, T. B. A., McCullen, P. A. J. & White, J. F. The effects of radiation on the corrosion of some Zr alloys. Corros. Sci. 10, 695–707 (1970).10.1016/S0010-938X(70)80041-5 ↗
13. He, M. R., Johnson, D. C., Was, G. S. & Robertson, I. M. The role of grain boundary microchemistry in irradiation-assisted stress corrosion cracking of a Fe–13Cr–15Ni alloy. Acta Mater. 138, 61–71 (2017).10.1016/j.actamat.2017.07.042 ↗
14. Raiman, S. S. & Was, G. S. Accelerated corrosion and oxide dissolution in 316L stainless steel irradiated in situ in high temperature water. J. Nucl. Mater. 493, 207–218 (2017).10.1016/j.jnucmat.2017.05.043 ↗
15. Zhang, H. et al. Nano-porosity effects on corrosion rate of Zr alloys using nanoscale microscopy coupled to machine learning. Corros. Sci. 208, 110660 (2022).10.1016/j.corsci.2022.110660 ↗
16. Hanbury, R. D. & Was, G. S. Oxide growth and dissolution on 316L stainless steel during irradiation in high temperature water. Corros. Sci. 157, 305–311 (2019).10.1016/j.corsci.2019.06.006 ↗
17. Zhou, W. et al. Proton irradiation-decelerated intergranular corrosion of Ni–Cr alloys in molten salt. Nat. Commun. 11, 3430 (2020).10.1038/s41467-020-17244-y ↗
18. Schmidt, F. et al. Effects of radiation-induced defects on corrosion. Annu. Rev. Mater. Res. 51, 293–328 (2021).10.1146/annurev-matsci-080819-123403 ↗
19. Wang, X. et al. Radiation-induced segregation in a ceramic. Nat. Mater. 19, 992–998 (2020).10.1038/s41563-020-0683-y ↗
20. Was, G. S. et al. Assessment of radiation-induced segregation mechanisms in austenitic and ferritic-martensitic alloys. J. Nucl. Mater. 411, 41–50 (2011).10.1016/j.jnucmat.2011.01.031 ↗
21. Doyle, P. et al. The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC. J. Nucl. Mater. 536, 152190 (2020).10.1016/j.jnucmat.2020.152190 ↗
22. Stoller, R. E. et al. On the use of SRIM for computing radiation damage exposure. Nucl. Instrum. Methods Phys. Res. Sect. B 310, 75–80 (2013).10.1016/j.nimb.2013.05.008 ↗
23. Xi, J., Liu, C., Morgan, D. & Szlufarska, I. Deciphering water-solid reactions during hydrothermal corrosion of SiC. Acta Mater. 209, 116803 (2021).10.1016/j.actamat.2021.116803 ↗
24. Xi, J., Liu, C., Morgan, D. & Szlufarska, I. An Unexpected Role of H during SiC Corrosion in Water. J. Phys. Chem. C 124, 9394–9400 (2020).10.1021/acs.jpcc.0c02027 ↗
25. Xi, J. & Szlufarska, I. Control of surface chemical reactions through solid stiffness. Phys. Rev. Lett. 129, 106101 (2022).10.1103/PhysRevLett.129.106101 ↗
26. Plimpton, S. Fast parallel algorithms for short-range molecular dynamics. J. Comput. Phys. 117, 1–19 (1995).10.1006/jcph.1995.1039 ↗
27. Shin, J. H., Kim, D., Lee, H. G., Park, J. Y. & Kim, W. J. Factors affecting the hydrothermal corrosion behavior of chemically vapor deposited silicon carbides. J. Nucl. Mater. 518, 350–356 (2019).10.1016/j.jnucmat.2019.03.026 ↗
28. Kondo, S., Lee, M., Hinoki, T., Hyodo, Y. & Kano, F. Effect of irradiation damage on hydrothermal corrosion of SiC. J. Nucl. Mater. 464, 36–42 (2015).10.1016/j.jnucmat.2015.04.034 ↗
29. Yeon, J. & Van Duin, A. C. T. ReaxFF molecular dynamics simulations of hydroxylation kinetics for amorphous and nano-silica structure, and its relations with atomic strain energy. J. Phys. Chem. C 120, 305–317 (2016).10.1021/acs.jpcc.5b09784 ↗
30. Fogarty, J. C., Aktulga, H. M., Grama, A. Y., Van Duin, A. C. T. & Pandit, S. A. A reactive molecular dynamics simulation of the silica-water interface. J. Chem. Phys. 132, 174704 (2010).10.1063/1.3407433 ↗
31. Newsome, D. A., Sengupta, D., Foroutan, H., Russo, M. F. & Van Duin, A. C. T. Oxidation of Silicon Carbide by O2 and H2O: A ReaxFF Reactive Molecular Dynamics Study, Part I. J. Phys. Chem. C 116, 16111–16121 (2012).10.1021/jp306391p ↗
32. Liu, C., Xi, J. & Szlufarska, I. Sensitivity of SiC grain boundaries to oxidation. J. Phys. Chem. C 123, 11546–11554 (2019).10.1021/acs.jpcc.9b00068 ↗
33. Xi, J., Liu, C. & Szlufarska, I. Effects of point defects on oxidation of 3C–SiC. J. Nucl. Mater. 538, 152308 (2020).10.1016/j.jnucmat.2020.152308 ↗
34. Allouche, A. Software news and updates gabedit—a graphical user interface for computational chemistry softwares. J. Comput. Chem. 32, 174–182 (2012).10.1002/jcc.21600 ↗
35. Vashishta, P., Kalia, R. K., Nakano, A. & Rino, J. P. Interaction potential for silicon carbide: a molecular dynamics study of elastic constants and vibrational density of states for crystalline and amorphous silicon carbide. J. Appl. Phys. 101, 103515 (2007).10.1063/1.2724570 ↗