Annealing behavior of hardening and ductility loss of a 16Cr-4Al ODS ferritic steel irradiated with high energy Ne ions
文献类型:期刊论文
作者 | Chen, Yuguang2,3; Zhang, Chonghong2,3![]() ![]() ![]() ![]() |
刊名 | JOURNAL OF NUCLEAR MATERIALS
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出版日期 | 2020-04-01 |
卷号 | 531页码:9 |
关键词 | ODS ferritic steel Irradiation Heavy ions Hardening Ductility loss |
ISSN号 | 0022-3115 |
DOI | 10.1016/j.jnucmat.2020.152030 |
通讯作者 | Zhang, Chonghong(c.h.zhang@impcas.ac.cn) |
英文摘要 | 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. Ne-20 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 mu m 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. (C) 2020 Elsevier B.V. All rights reserved. |
WOS关键词 | EUROFER ; INDENTATION ; CORROSION ; CLUSTERS ; METALS ; DAMAGE |
资助项目 | National Key Research and Development Program of China[2017YFB0702202] ; National Natural Science Foundation of China[U1532262] ; National Magnetic Confinement Fusion Program[2011GB108003] |
WOS研究方向 | Materials Science ; Nuclear Science & Technology |
语种 | 英语 |
WOS记录号 | WOS:000518889500003 |
出版者 | ELSEVIER |
资助机构 | National Key Research and Development Program of China ; National Natural Science Foundation of China ; National Magnetic Confinement Fusion Program |
源URL | [http://119.78.100.186/handle/113462/140608] ![]() |
专题 | 中国科学院近代物理研究所 |
通讯作者 | Zhang, Chonghong |
作者单位 | 1.Kyoto Univ, Inst Adv Energy, Kyoto 6110011, Japan 2.Univ Chinese Acad Sci, Sch Nucl Sci & Technol, Beijing 100049, Peoples R China 3.Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China |
推荐引用方式 GB/T 7714 | Chen, Yuguang,Zhang, Chonghong,Ding, Zhaonan,et al. Annealing behavior of hardening and ductility loss of a 16Cr-4Al ODS ferritic steel irradiated with high energy Ne ions[J]. JOURNAL OF NUCLEAR MATERIALS,2020,531:9. |
APA | Chen, Yuguang.,Zhang, Chonghong.,Ding, Zhaonan.,Zhang, XianLong.,Yang, Yitao.,...&Kimura, Akihiko.(2020).Annealing behavior of hardening and ductility loss of a 16Cr-4Al ODS ferritic steel irradiated with high energy Ne ions.JOURNAL OF NUCLEAR MATERIALS,531,9. |
MLA | Chen, Yuguang,et al."Annealing behavior of hardening and ductility loss of a 16Cr-4Al ODS ferritic steel irradiated with high energy Ne ions".JOURNAL OF NUCLEAR MATERIALS 531(2020):9. |
入库方式: OAI收割
来源:近代物理研究所
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