journal article·2020-04

Annealing behavior of hardening and ductility loss of a 16Cr–4Al ODS ferritic steel irradiated with high energy Ne ions

Yuguang Chen, Chonghong Zhang, Zhaonan Ding, XianLong Zhang, Yitao Yang, Yin Song, Akihiko Kimura

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Abstract

Abstract Annealing behavior of the hardening and ductility loss of an oxide-dispersion-strengthened (ODS) ferritic steel (16Cr–4Al) irradiated with high-energy heavy ions is studied. 20Ne ions with 123.4 MeV supplied by a cyclotron was used to produce a quasi-uniform atomic region of atomic displacement damage and Ne concentration from surface to a depth of 33 μm in the specimens. Two atomic displacement levels (0.16dpa, 0.70dpa) were approached at about 220 K. The irradiated specimens were subsequently thermally annealed at room temperature, 473 K and 673 K, respectively. Hardness and ductility of the specimens were investigated with nano-indentation technique and small-punch test. The data of the nano hardness were fitted by Nix-Gao model to obtain the bulk equivalent hardness values. The irradiated specimens show observable hardening, which recedes monotonously with the increase of annealing temperature. The Arrhenius plots show a good linearity in the entire temperature range investigated, with an apparent activation energy of 0.13 ± 0.01 eV for both the two damage levels. Assuming that the hardening is caused by the self-interstitial-atom (SIA) clusters initially produced by the cascade damage, an activation energy of 0.70 ± 0.05 eV is deduced for the migration and coalescence process of the SIA-clusters. The small punch test (SPT) of the high-dose specimens shows that a minor ductility loss occurred under conditions as-irradiated or subsequently thermally annealed at 473 K, while a remarkable increase of the ductility loss was observed after the thermal annealing at 673 K, which coincides with the formation of nano-scale gas bubbles in high density in the specimen. It is indicated that the formation of bubbles has minor on the irradiation hardening. A comparison of three ODS ferritic steels Ne-ion-irradiated to 0.7 dpa/260 appm(Ne) shows that the ductility loss decreases with the increase of the sink strength of the oxide dispersoids/ferritic substrate interfaces.
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OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Ion-surface interactions and analysis

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References (29)

Show source-provided references
1. Present development status of EUROFER and ODS-EUROFER for application in blanket concepts10.1016/j.fusengdes.2005.06.186 ↗
2. On the role of alloy composition and processing parameters in nanocluster formation and dispersion strengthening in nanostuctured ferritic alloys10.1016/j.actamat.2008.09.025 ↗
3. Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems10.1016/j.jnucmat.2010.12.300 ↗
4. Fabrication and characterization of reference 9Cr and 12Cr-ODS low activation ferritic/martensitic steels10.1016/j.fusengdes.2014.01.010 ↗
5. Structural materials for fission & fusion energy10.1016/S1369-7021(09)70294-9 ↗
6. Annealing behavior of irradiation hardening and microstructure in helium-implanted reduced activation martensitic steel10.1016/S0022-3115(00)00090-8 ↗
7. Repeatability of irradiation damage and of recovery by post-irradiation annealing of EUROFER base steels10.1016/j.fusengdes.2017.04.066 ↗
8. Recent insights on the swelling and creep of irradiated austenitic alloys10.1016/0022-3115(84)90641-X ↗
9. Corrosion of austenitic and martensitic stainless steels in flowing 17Li-83Pb alloy10.1016/0022-3115(88)90401-1 ↗
10. Comparison of corrosion behavior of bare and hot-dip coated EUROFER steel in flowing Pb–17Li10.1016/j.jnucmat.2007.03.205 ↗
11. Development of oxide dispersion strengthened ferritic steels for FBR core application, (I)10.1080/18811248.1997.9733658 ↗
12. Irradiation response of ODS ferritic steels to high-energy Ne ions at HIRFL10.1016/j.jnucmat.2014.04.015 ↗
13. Hardening of ODS ferritic steels under irradiation with high-energy heavy ions10.1016/j.jnucmat.2017.05.040 ↗
14. Ziegler · 1984 · 1
15. Small-punch technique for measurement of material degradation of irradiated ferritic alloys
16. Hardening of an ODS ferritic steel after helium implantation and thermal annealing10.1088/0256-307X/35/5/056102 ↗
17. Application of small-scale testing for investigation of ion-beam-irradiated materials10.1557/jmr.2012.303 ↗
18. Issues to consider using nano indentation on shallow ion beam irradiated materials10.1016/j.jnucmat.2011.11.070 ↗
19. Indentation size effects in crystalline materials: a law for strain gradient plasticity10.1016/S0022-5096(97)00086-0 ↗
20. Assessment of the constitutive properties from small ball punch test: experiment and modeling10.1016/j.jnucmat.2004.07.052 ↗
21. On the modeling of the high-temperature embrittlement of metals containing helium10.1016/0022-3115(83)90177-0 ↗
22. Was · 2007
23. Dislocation loop structure, energy and mobility of self-interstitial atom clusters in bcc iron10.1016/S0022-3115(99)00166-X ↗
24. Formulating the strength factor α for improved predictability of radiation hardening10.1016/j.jnucmat.2015.07.009 ↗
25. Progress in modelling the microstructural evolution in metals under cascade damage conditions10.1016/S0022-3115(00)00332-9 ↗
26. Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys10.1038/ncomms13564 ↗
27. One-dimensional migration of interstitial clusters in SUS316L and its model alloys at elevated temperatures10.1080/14786435.2015.1040100 ↗
28. Observation of the one-dimensional diffusion of nanometer-sized dislocation loops10.1126/science.1145386 ↗
29. Characterization of the oxide particles in Al-added high-Cr ODS ferritic steels10.1016/j.jnucmat.2010.12.063 ↗