Plasma-facing components damage and its effects on plasma performance in EAST tokamak
文献类型：期刊论文
| 作者 | Gao, Binfu1,2; Ding, Rui2 ; Xie, Hai2,3; Zeng, Long2; Zhang, Ling2; Wang, Baoguo1; Li, Changjun1,2; Zhu, Dahuan2; Yan, Rong2; Chen, Junling2
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| 刊名 | FUSION ENGINEERING AND DESIGN
 |
| 出版日期 | 2020-07-01 |
| 卷号 | 156 |
| 关键词 | Hot spot W melting Disruptions Radiation EAST tokamak |
| ISSN号 | 0920-3796 |
| DOI | 10.1016/j.fusengdes.2020.111616 |
| 通讯作者 | Ding, Rui(rding@ipp.ac.cn) |
| 英文摘要 | During the tokamak operations, plasma-wall interactions (PWI) can severely damage the plasma-facing cornponents (PFCs), which will lead to degradation of plasma performance due to radiation losses by the impurities released from the damaged PFCs surfaces. The PFCs damage and its effects on the plasma performance are studied experimentally for the EAST tokamak. Substantial dusts were generated from the hot spots at the guard limiter of LHCD antenna and the tungsten (W) melting processes from the W upper divertor, which results in disruption due to high radiation losses. Two methods can be effectively used to recover the plasma discharges after tungsten melting induced disruptions, reducing the auxiliary heating power or moving away the position of strike point from the melting site. Statistics analysis indicate that about 12.0 % and 38.3 % of disruptions were due to severe impurity burst from the strong PWI processes in 2017 and 2018 campaign, respectively. In 2018 campaign, the plasma disruption due to tungsten impurity burst is about 26.3 %, which is much higher than 4.8 % in 2017 campaign. This is due to the higher auxiliary heating power, larger misalignment on W PFCs and the new W guard limiter. The main features on the effects of PFC damage on plasma operation are shown. |
| WOS关键词 | GUARD LIMITER |
| 资助项目 | National Key Research and Development Program of China[2017YFE0301300] ; National Key Research and Development Program of China[2017YFE0300500] ; National Key Research and Development Program of China[2017YFA0402500] ; National Nature Science Foundation of China[11675218] ; National Nature Science Foundation of China[11575244] ; National Nature Science Foundation of China[11861131010] ; CASHIPS Director's Fund[BJPY2019B01] ; Key Research Program of Frontier Sciences of CAS[ZDBS-LY-SLH010] |
| WOS研究方向 | Nuclear Science & Technology |
| 语种 | 英语 |
| WOS记录号 | WOS:000540064300009 |
| 出版者 | ELSEVIER SCIENCE SA |
| 资助机构 | National Key Research and Development Program of China ; National Nature Science Foundation of China ; CASHIPS Director's Fund ; Key Research Program of Frontier Sciences of CAS |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/103051]  |
| 专题 | 中国科学院合肥物质科学研究院 |
| 通讯作者 | Ding, Rui |
| 作者单位 | 1.Univ Sci & Technol China, Hefei 230031, Peoples R China 2.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China 3.Shenzhen Univ, Adv Energy Res Ctr, Shenzhen 518060, Peoples R China |
| 推荐引用方式 GB/T 7714 | Gao, Binfu,Ding, Rui,Xie, Hai,et al. Plasma-facing components damage and its effects on plasma performance in EAST tokamak[J]. FUSION ENGINEERING AND DESIGN,2020,156. |
| APA | Gao, Binfu.,Ding, Rui.,Xie, Hai.,Zeng, Long.,Zhang, Ling.,...&Chen, Junling.(2020).Plasma-facing components damage and its effects on plasma performance in EAST tokamak.FUSION ENGINEERING AND DESIGN,156. |
| MLA | Gao, Binfu,et al."Plasma-facing components damage and its effects on plasma performance in EAST tokamak".FUSION ENGINEERING AND DESIGN 156(2020). |
入库方式： OAI收割
来源：合肥物质科学研究院
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