Impact of neutron irradiation on hardening of baseline and advanced tungsten grades and its link to initial microstructure
文献类型：期刊论文
| 作者 | Yin,Chao6,7; Terentyev,Dmitry7; Dubinko,Andrii7; Zhang,Tao5 ; Wirtz,Marius4; Antusch,Steffen3; Petrov,Roumen H.1,2; Pardoen,Thomas6
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| 刊名 | Nuclear Fusion
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| 出版日期 | 2021-04-29 |
| 卷号 | 61 |
| 关键词 | tungsten neutron irradiation irradiation hardening microindentation |
| ISSN号 | 0029-5515 |
| DOI | 10.1088/1741-4326/abf417 |
| 通讯作者 | Yin,Chao() ; Petrov,Roumen H.() |
| 英文摘要 | AbstractSix tungsten grades were irradiated in the Belgian material test reactor (BR2) and characterized by Vickers hardness tests in order to investigate the irradiation-induced hardening. These tungsten grades included: Plansee (Austria) ITER specification tungsten, ALMT (Japan) ITER specification tungsten, two products from KIT (Germany) produced by powder injection molding (PIM) and strengthened by 1% TiC and 2% Y2O3 dispersed particles, and rolled tungsten strengthened by 0.5% ZrC from ISSP (China). The materials were irradiated face-to-face at three temperatures equal to 600 °C, 1000 °C, and 1200 °C to the dose of ～1 dpa. The Vickers hardness tests under 200 gf (HV0.2) were performed at room temperature. The Vickers hardness increases as the irradiation temperature increases from 600 to 1000 °C for all materials, except for the ZrC-reinforced tungsten, for which the increase of hardness does not depend on irradiation temperature. The irradiation-induced hardness decreases after irradiation at 1200 °C. This is a result of defect annealing enhanced by thermally activated diffusion. However, even at 1200 °C, the impact of neutron irradiation on the hardness increase remains significant; the hardness increases by ～30 to 60% compared to the non-irradiated value. In the case of TiC-strengthened material, the irradiation hardening progressively raises with irradiation temperature, which cannot be explained by the accumulation of neutron irradiation defects solely. |
| 语种 | 英语 |
| WOS记录号 | IOP:0029-5515-61-6-ABF417 |
| 出版者 | IOP Publishing |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/121843]  |
| 专题 | 中国科学院合肥物质科学研究院 |
| 通讯作者 | Yin,Chao; Petrov,Roumen H. |
| 作者单位 | 1.Department of Materials Science and Engineering, Delft University of Technology, Delft, 2082, Netherlands 2.Department of Electrical Energy, Metals, Mechanical Constructions & Systems, Ghent University, 9052, Ghent, Belgium 3.Karlsruhe Institute of Technology (KIT), Institute for Applied Materials, 76344 Eggenstein-Leopoldshafen, Germany 4.Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung, 52425 Jülich, Germany 5.Institute of Solid State Physics, Chinese Academy of Sciences, Hefei, Anhui 230031, China 6.Institute of Mechanics, Materials and Civil Engineering, UCLouvain, 1348 Louvain-la-Neuve, Belgium 7.Structural Materials Group, Institute of Nuclear Materials Science, SCK CEN, 2400 Mol, Belgium |
| 推荐引用方式 GB/T 7714 | Yin,Chao,Terentyev,Dmitry,Dubinko,Andrii,et al. Impact of neutron irradiation on hardening of baseline and advanced tungsten grades and its link to initial microstructure[J]. Nuclear Fusion,2021,61. |
| APA | Yin,Chao.,Terentyev,Dmitry.,Dubinko,Andrii.,Zhang,Tao.,Wirtz,Marius.,...&Pardoen,Thomas.(2021).Impact of neutron irradiation on hardening of baseline and advanced tungsten grades and its link to initial microstructure.Nuclear Fusion,61. |
| MLA | Yin,Chao,et al."Impact of neutron irradiation on hardening of baseline and advanced tungsten grades and its link to initial microstructure".Nuclear Fusion 61(2021). |
入库方式： OAI收割
来源：合肥物质科学研究院
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