journal article·2016-04Open access

Effect of chromium on void swelling in ion irradiated high purity Fe–Cr alloys

A. Bhattacharya, E. Meslin, J. Henry, A. Barbu, S. Poissonnet, B. Décamps

Acta Materialia· Volume 108

Abstract

The concentration of chromium (Cr) plays an important role on the radiation induced microstructure of the binary Fe–Cr alloys, in particular on the formation of cavities leading to void swelling of the material. Many fast neutron irradiations were performed in the past to understand the swelling variation as a function of the Cr content. However, due to some contrasting results in the literature, the trend is not yet clear. For that purpose, we have performed self-ion irradiations to high doses (>100 dpa) at 773 K, in single beam mode (damage by 2 MeV self ions) and dual beam mode (damage by 2 MeV self-ions and co-implantation of 2 MeV helium ions with continuous energy degradation) on a wide range of high purity Fe–Cr alloys with Cr level ranging from 3 wt.% to 14 wt.% and a reference body centred cubic (bcc) iron (Fe). Conventional transmission electron microscopy (TEM) analysis revealed a strong swelling suppression by the addition of 3 wt.% Cr to the Fe matrix. The analysis of the dual beam irradiated samples revealed that the variation of void swelling as a function of the Cr content is non-monotonic, with a local swelling maxima around 9–10 wt.% Cr. Overall, all the Fe–Cr alloys up to 14 wt.% Cr show much reduced swelling as compared to bcc Fe. No cavities, and hence, swelling, was noted in the single beam irradiated Fe–Cr alloys, while the same in bcc Fe remained high. This elucidates further the large magnitude of swelling reduction by Cr.
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Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Nuclear materials and radiation effects

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References (70)

Show source-provided references
1. Fissile core and tritium-breeding blanket: structural materials and their requirements10.1016/j.crhy.2007.11.004 ↗
2. On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors10.1088/0029-5515/44/1/006 ↗
3. Klueh · 2001
4. Void-swelling in iron and ferritic steels: II. An experimental survey of materials irradiated in a fast reactor10.1016/0022-3115(79)90123-5 ↗
5. Microstructural examination of neutron-irradiated simple ferritic alloys10.1016/0022-3115(82)90523-2 ↗
6. Void swelling in binary Fe-Cr alloys at 200 dpa10.1016/0022-3115(95)00053-4 ↗
7. Swelling and dislocation evolution in simple ferritic alloys irradiated to high fluence in FFTF/MOTA10.1016/0022-3115(94)00669-5 ↗
8. 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 ↗
9. 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 ↗
10. Positron annihilation spectroscopy on binary Fe-Cr alloys and ferritic/martensitic steels after neutron irradiation10.1016/j.actamat.2011.06.046 ↗
11. Characterization of dislocation loops and chromium-rich precipitates in ferritic iron–chromium alloys as means of void swelling suppression10.1016/j.jnucmat.2007.01.069 ↗
12. Dynamic observations of heavy-ion damage in Fe and Fe–Cr alloys10.1016/j.jnucmat.2009.02.003 ↗
13. Characteristics of point defects and their clustering in pure ferritic steels10.1016/0022-3115(88)90502-8 ↗
14. He and Cr effects on radiation damage formation in ion-irradiated pure iron and Fe–5.40 wt.% Cr: A transmission electron microscopy study10.1016/j.actamat.2013.04.070 ↗
15. The need for improved temperature control during reactor irradiation10.1016/0022-3115(88)90040-2 ↗
16. Fission-fusion correlation by fission reactor irradiation with improved control10.1016/0022-3115(90)90245-I ↗
17. Influence of details of reactor history on microstructural development during neutron irradiation10.1016/0022-3115(93)90083-B ↗
18. The microstructure of triple-beam ion irradiated Fe and Fe-Cr alloys10.1016/0022-3115(82)90745-0 ↗
19. Void swelling of ferritic alloys bombarded with nickel ions
20. Void swelling and segregation of solute in ion-irradiated ferritic steels10.1016/0022-3115(82)90751-6 ↗
21. Synergistic effect of helium and hydrogen for defect evolution under multi-ion irradiation of Fe-Cr ferritic alloys10.1016/j.jnucmat.2004.04.051 ↗
22. 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 ↗
23. Correlation of neutron and heavy-ion damage: II. The predicted temperature shift of swelling with changes in radiation dose10.1016/0022-3115(78)90514-7 ↗
24. Correlation of neutron and heavy-ion damage: I. The influence of dose rate and injected helium on swelling in pure nickel10.1016/0022-3115(78)90513-5 ↗
25. Swelling behavior of commercial ferritic alloys, EM-12 and HT-9, as assessed by heavy ion bombardment
26. Microstructural developments in Fe-Cr-W low activation ferritic steels under dual beam charged particle irradiation10.1016/0022-3115(91)90187-C ↗
27. Radiation damage simulation studies in the Harwell VEC of selected austenitic and ferritic alloys for fusion applications10.1016/0022-3115(88)90436-9 ↗
28. Behaviour of different ferritic steels under ion, electron and fast neutron irradiation10.1016/0022-3115(88)90509-0 ↗
29. Cavity formation during single and dual ion irradiation in a 9Cr-1Mo ferritic alloy10.1016/0022-3115(83)90070-3 ↗
30. Microstructural evolution of HT9 under dual beam charged particle irradiation10.1016/0022-3115(88)90440-0 ↗
31. Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa10.1016/j.jnucmat.2014.06.011 ↗
32. Ion bombardment damage in a modified Fe-9Cr-1Mo steel
33. Radiation swelling of ferritic-martensitic steels EP-450 and HT-9 under irradiation by metallic ions to super-higher doses, Problems of Atomic Science and Technology
34. The void swelling behaviour of electron irradiated type 316 austenitic steel10.1016/0022-3115(80)90090-2 ↗
35. The role of minor alloying elements in swelling of 316 steel10.1016/0022-3115(92)90689-I ↗
36. Effects of alloying elements on the post-irradiation microstructure of 9%Cr-2%W low activation martensitic steels10.1016/0022-3115(92)90599-G ↗
37. A study of the effect of titanium on the void swelling behavior of D9 steels by ion beam simulation10.1016/j.jnucmat.2008.08.049 ↗
38. Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix10.1016/0022-3115(93)90080-I ↗
39. J. Le Coze, reportFinal Report on Model Alloy Preparation ;EFDA - Contract 06-1901 TW6-ttms 007- PUREFE.
40. Fraczkeiwicz · 2011
41. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
42. Spatial variation in void volume during charged particle bombardment — the effects of injected interstitials10.1016/0022-3115(79)90548-8 ↗
43. Effect of self-ion injection in simulation studies of void swelling10.1016/0022-3115(77)90194-5 ↗
44. Suppression of void nucleation by injected interstitials during heavy ion bombardment10.1016/0022-3115(84)90062-X ↗
45. Impact of the injected interstitial on the correlation of charged particle and neutron-induced radiation damage10.1016/0022-3115(83)90023-5 ↗
46. Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions10.1016/j.jnucmat.2014.06.002 ↗
47. Jenkins · 2001
48. R. F. Egerton, Electron energy-loss spectroscopy in the TEM, Rep. Prog. Phys. 72 (1) 016502.10.1088/0034-4885/72/1/016502 ↗
49. Chromium enrichment on the habit plane of dislocation loops in ion-irradiated high purity Fe-Cr alloys10.1016/j.actamat.2014.06.050 ↗
50. Radiation-induced α′ phase formation on dislocation doops in Fe-Cr alloys during electron irradiation
51. Effects of irradiation temperature and dose rate on the mechanical properties of self-ion implanted Fe and Fe–Cr alloys10.1016/j.jnucmat.2013.03.052 ↗
52. Bhattacharya · 2014
53. Positron annihilation lifetime measurement of electron-irradiated Fe-Cr alloys10.4028/www.scientific.net/MSF.105-110.1125 ↗
54. Effects of radiation-induced defects on microstructural evolution of Fe-Cr model alloys10.1016/j.jnucmat.2008.12.079 ↗
55. Ab initio study of Cr interactions with point defects in bcc Fe10.1103/PhysRevB.75.014110 ↗
56. Radiation-induced effects on microstructure
57. Effect of alloying elements on irradiation hardening behavior and microstructure evolution in BCC Fe10.1016/j.jnucmat.2013.04.035 ↗
58. Interaction between helium and self-defects in α-iron from first principles10.1016/j.jnucmat.2007.03.002 ↗
59. Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 2: Damage evolution in thin-foils at higher doses10.1080/14786430802380477 ↗
60. Effects of chromium on the one-dimensional motion of interstitial-type dislocation loops in iron10.1016/j.jnucmat.2004.04.263 ↗
61. Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 1: Damage evolution in thin-foils at lower doses10.1080/14786430802380469 ↗
62. Was · 2007
63. Impact of He and Cr on defect accumulation in ion-irradiated ultrahigh-purity Fe(Cr) alloys10.1016/j.actamat.2013.08.007 ↗
64. Dislocation loops in irradiated iron10.1038/200254a0 ↗
65. A microstructural explanation for the low swelling of ferritic steels
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. α′ precipitation in neutron-irradiated Fe–Cr alloys10.1016/j.scriptamat.2013.10.001 ↗
68. Effects of heavy ion irradiation on HT-9 ferritic steel examined in cross section
69. Radiation damage studies of the 10 to 13% chromium-containing steels and alloys irradiated with heavy ions
70. Ion-irradiation-induced damage in Fe–Cr alloys characterized by nanoindentation10.1016/j.jnucmat.2010.12.196 ↗