Temperature-dependent cavity swelling in dual-ion irradiated Fe and Fe-Cr ferritic alloys
Source abstract
Abstract
Fe-Cr ferritic-martensitic (FM) steels are promising structural material candidates for fusion and advanced fission reactors due to their attractive mechanical properties and volumetric swelling resistance. However, significant discrepancies exist regarding the effect of solutes and irradiation temperature on cavity swelling under ion versus neutron irradiation conditions. In this study, simultaneous dual ion irradiations (8 MeV Ni 3+ ions and energy-degraded 3.5 MeV He 2+ ions) were used to quantify the cavity swelling behavior in ultra-high purity Fe and Fe-Cr alloys (3-14 wt.% Cr), Fe-10 wt.% Cr-780 wt.ppm C, and Eurofer97 FM steel. The irradiations were conducted over a wide temperature range (400-550°C) with a mid-range dose of ~30 displacements per atom (dpa) and 0.1 appm/dpa He implantation rate. Using state-of-the-art transmission electron microscopy (TEM), we reveal that pure Fe has a ~50°C lower peak swelling temperature difference than Fe-Cr alloys, which is attributed to higher vacancy mobility in pure Fe. Chromium solute appears to strongly suppress cavity swelling in Fe-Cr alloys for temperatures below ~470°C, but seems to have little effect or slightly enhances swelling above ~470°C. Cavities were observed in all the irradiated samples between 400-550°C. This indicates that the narrow temperature range of observable cavities reported in prior ion irradiated Fe-Cr ferritic alloy studies is likely an artifact associated with the use of low ion energies (<5 MeV), which leads to pronounced near-surface and implanted ion effects that suppress cavity swelling even at midrange depths (particularly at high temperatures).
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Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Ion-surface interactions and analysis
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (78)
Show source-provided references
1. Chapter 11 - Ferritic and tempered martensitic steels
2. History of power plants and progress in heat resistant steels10.2355/isijinternational.41.612 ↗
3. Chapter 8 - Austenitic stainless steels
4. F.A. Smidt, P.R. Malmberg, J.A. Sprague, J.E. Westmoreland, Swelling Behavior of Commercial Ferritic Alloys, EM-12 and HT-9, as Assessed by Heavy Ion Bombardment, in: F.R. Shober (Ed.), ASTM International, West Conshohocken, PA, 1976, pp. 227-241.10.1520/STP38051S ↗
5. The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels10.1016/j.jnucmat.2016.12.006 ↗
6. Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions10.1016/j.jnucmat.2017.02.006 ↗
7. A TEM study of neutron-irradiated iron10.1016/0022-3115(82)90490-1 ↗
8. Void-swelling in irons and ferritic steels: I. Mechanisms of swelling suppression10.1016/0022-3115(79)90122-3 ↗
9. Opportunities and limitations for ion beams in radiation effects studies: bridging critical gaps between charged particle and neutron irradiations10.1016/j.scriptamat.2017.06.041 ↗
10. Interaction between vacancies and interstitial solutes (C, N, and O) in $\ensuremath{\alpha}\text{\ensuremath{-}}\mathrm{Fe}$: From electronic structure to thermodynamics10.1103/PhysRevB.90.054112 ↗
11. The resistivity recovery of high purity and carbon doped iron following low temperature electron irradiation10.1080/00337578308207398 ↗
12. On the interaction between radiation-induced defects and foreign interstitial atoms in α-iron10.1016/j.jnucmat.2011.04.061 ↗
13. Formation of voids in iron during high temperature neutron irradation10.1080/00337576908235581 ↗
14. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure10.1016/S0022-3115(99)00225-1 ↗
15. Experimental studies of cascade phenomena in metals10.1016/0022-3115(93)90067-9 ↗
16. Advances in void swelling and helium bubble physics10.1016/0022-3115(84)90626-3 ↗
17. Sniegowski · 1984
18. The microstructure and tensile properties of Fe–Cr alloys after neutron irradiation at 400°C to 5.5–7.1 dpa10.1016/S0022-3115(98)00043-9 ↗
19. Microstructural examination of neutron-irradiated simple ferritic alloys10.1016/0022-3115(82)90523-2 ↗
20. Effects of irradiation on ferritic alloys and implications for fusion reactor applications10.1016/0022-3115(87)90477-6 ↗
21. Compositional and temperature dependence of void swelling in model Fe–Cr base alloys irradiated in the EBR-II fast reactor10.1016/S0022-3115(00)00338-X ↗
22. Swelling and dislocation evolution in simple ferritic alloys irradiated to high fluence in FFTF/MOTA10.1016/0022-3115(94)00669-5 ↗
23. Void swelling in binary FeCr alloys at 200 dpa10.1016/0022-3115(95)00053-4 ↗
24. Effects of dpa rate on swelling in neutron-irradiated Fe–Cr and Fe–Cr–Mo alloys10.1016/j.jnucmat.2010.12.167 ↗
25. The microstructure of “triple-beam” ion irradiated Fe and Fe-Cr alloys10.1016/0022-3115(82)90745-0 ↗
26. Effect of chromium on void swelling in ion irradiated high purity Fe–Cr alloys10.1016/j.actamat.2016.02.027 ↗
27. Dramatic reduction of void swelling by helium in ion-irradiated high purity α-iron10.1080/21663831.2018.1462266 ↗
28. He and Cr effects on radiation damage formation in ion-irradiated pure iron and Fe–5.40wt.% Cr: A transmission electron microscopy study10.1016/j.actamat.2013.04.070 ↗
29. W.G. Johnston, T. Lauritzen, J.H. Rosolowski, A.M. Turkalo, Void Swelling of Ferritic Alloys Bombarded with Nickel Ions, in: H.R. Brager, J.S. Perrin (Eds.), ASTM International, West Conshohocken, PA, 1982, pp. 809-823.10.1520/STP34381S ↗
30. Neutron interactions and atomic recoil spectra10.1016/0022-3115(94)90004-3 ↗
31. Synergistic influence of displacement rate and helium/dpa ratio on swelling of Fe–(9, 12)Cr binary alloys in FFTF at ~400°C10.1016/j.jnucmat.2004.04.346 ↗
32. Coze Le · 2007
33. Resolution of the carbon contamination problem in ion irradiation experiments10.1016/j.nimb.2017.08.039 ↗
34. Multiple ion beam irradiation for the study of radiation damage in materials10.1016/j.nimb.2017.08.035 ↗
35. Modeling the impact of radiation-enhanced diffusion on implanted ion profiles10.1016/j.jnucmat.2018.06.042 ↗
36. On the use of SRIM for calculating vacancy production: quick calculation and full-cascade options
37. SRIM – the stopping and range of ions in matter (2010)10.1016/j.nimb.2010.02.091 ↗
38. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
39. Low-loss and no-loss spectra and images
40. Impact of the injected interstitial on the correlation of charged particle and neutron-induced radiation damage10.1016/0022-3115(83)90023-5 ↗
41. Suppression of void nucleation by injected interstitials during heavy ion bombardment10.1016/0022-3115(84)90062-X ↗
42. Influence of irradiation parameters on damage accumulation in metals and alloys10.1016/0022-3115(94)90316-6 ↗
43. Impact of glissile interstitial loop production in cascades on defect accumulation in the transient10.1016/0022-3115(93)90124-H ↗
44. Dual-beam irradiation of α-iron: Heterogeneous bubble formation on dislocation loops10.1016/j.jnucmat.2011.06.048 ↗
45. D.S. Gelles, R.M. Claudson, L.E. Thomas, Quantitative analysis of void swelling, fusion reactor materials semiannual progress report DOE/ER-0313/3 (1987) 131-136.
46. Theory and experimental background on dimensional changes in irradiated alloys10.1016/0022-3115(94)90009-4 ↗
47. Mechanisms of helium interaction with radiation effects in metals and alloys: a review10.1016/0022-3115(83)90047-8 ↗
48. S.J. Zinkle, A Brief Review of Radiation-Induced Cavity Swelling and Hardening in Copper and Copper Alloys, in: R.E. Stoller, A.S. Kumar, D.S. Gelles (Eds.), ASTM International, West Conshohocken, PA, 1992, pp. 813-834.10.1520/STP17913S ↗
49. Synergistic effect of helium and hydrogen for defect evolution under multi-ion irradiation of Fe–Cr ferritic alloys10.1016/j.jnucmat.2004.04.051 ↗
50. Simulation irradiation studies on iron10.1016/0022-3115(82)90746-2 ↗
51. The effect of triple ion beam irradiation on cavity formation on pure EFDA iron10.1016/j.jnucmat.2016.06.043 ↗
52. TEM study and modeling of bubble formation in dual-beam He+/Fe3+ ion irradiated EUROFER9710.1016/j.jnucmat.2016.11.014 ↗
53. Use of double and triple-ion irradiation to study the influence of high levels of helium and hydrogen on void swelling of 8–12% Cr ferritic-martensitic steels10.1016/j.jnucmat.2015.07.012 ↗
54. Correlation of neutron and heavy-ion damage: II. The predicted temperature shift if swelling with changes in radiation dose rate10.1016/0022-3115(78)90514-7 ↗
55. Density functional theory models for radiation damage10.1146/annurev-matsci-071312-121626 ↗
56. Multiscale modelling of defect kinetics in irradiated iron10.1038/nmat1286 ↗
57. Baroch · 1975
58. S.J. Zinkle, Dislocation Loop Formation in Ion-Irradiated Polycrystalline Spinel and Alumina, in: R.E. Stoller, A.S. Kumar, D.S. Gelles (Eds.), ASTM International, West Conshohocken, PA, 1992, pp. 749-763.10.1520/STP17908S ↗
59. Vacancy migration energy dependence on local chemical environment in Fe–Cr alloys: a density functional theory study10.1016/j.jnucmat.2014.05.007 ↗
60. 1.01 Fundamental properties of defects in metals
61. α′ Formation kinetics and radiation induced segregation in neutron irradiated 14YWT nanostructured ferritic alloys10.1038/s41598-019-44508-5 ↗
62. Void swelling and defect cluster formation in reactor-irradiated copper10.1016/0022-3115(89)90591-6 ↗
63. Neutron-induced swelling and embrittlement of pure iron and pure nickel irradiated in the BN-350 and BOR-60 fast reactors10.1016/j.jnucmat.2008.01.015 ↗
64. Damage in neutron-irradiated molybdenum: (I). Characterization of as-irradiated microstructure10.1016/0022-3115(74)90144-5 ↗
65. Ab initio study of solute transition-metal interactions with point defects in bcc Fe10.1103/PhysRevB.81.054102 ↗
66. Behaviour of P, Si, Ni impurities and Cr in self ion irradiated Fe–Cr alloys – comparison to neutron irradiation10.1016/j.jnucmat.2014.10.024 ↗
67. Influence of injected interstitials on α′ precipitation in Fe–Cr alloys under self-ion irradiation10.1080/21663831.2016.1230896 ↗
68. Zhao, S.J. Zinkle, A. Bhattacharya, Alpha-prime precipitate formation in ion irradiated Fe14Cr and Fe18Cr alloys Fusion Materials Semiannual Progress Reports 66 (2019) 3.
69. Dose rate dependence of Cr precipitation in an ion-irradiated Fe18Cr alloy10.1016/j.scriptamat.2017.11.040 ↗
70. Vacancy-solute clustering in Fe–Cr alloys after neutron irradiation10.1016/j.jnucmat.2020.152341 ↗
71. Dynamic observations of heavy-ion damage in Fe and Fe–Cr alloys10.1016/j.jnucmat.2009.02.003 ↗
72. Microstructural evolution in dual-ion irradiated 316ss under various helium injection schedules10.1016/0022-3115(84)90600-7 ↗
73. Experimental effects of helium on cavity formation during irradiation—a review10.1080/00337578008207114 ↗
74. Modification of radiation damage microstructure by helium10.1080/00337578308207378 ↗
75. 1.12 - Cavity swelling in irradiated materials
76. L.L. Horton, L.K. Mansur, Experimental Determination of the Critical Cavity Radius in Fe-10Cr for Ion Irradiation, in: F.A. Garner, J.S. Perrin (Eds.), ASTM International, West Conshohocken, PA, 1985, pp. 344-362.10.1520/STP37372S ↗
77. Analytical solutions for helium bubble and critical radius parameters using a hard sphere equation of state10.1016/0022-3115(85)90450-7 ↗
78. Ion bombardment damage in a modified Fe-9Cr-1Mo steel