Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments
文献类型：期刊论文
| 作者 | Guo, Zongxiao1,2; Zhu, Dahuan2 ; Yan, Rong2; Xuan, Chuannan1,2; Wang, Baoguo2; Wang, Yang1,2; Gao, Binfu1,2; He, Chunyu1,2; Ding, Rui2; Li, Yi1,2
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| 刊名 | NUCLEAR FUSION
 |
| 出版日期 | 2024-07-01 |
| 卷号 | 64 |
| 关键词 | W/Cu monoblocks damages transient heat flux heat exhaust capacity EAST ITER |
| ISSN号 | 0029-5515 |
| DOI | 10.1088/1741-4326/ad4a8b |
| 通讯作者 | Zhu, Dahuan(dhzhu@ipp.ac.cn) ; Wang, Baoguo(wbg2014@ipp.ac.cn) |
| 英文摘要 | In the ITER and future fusion devices, W/Cu monoblocks will be used as divertor target which are exposed to both steady state heat load and transient heat flux. Especially, the transient heat flux up to 10 GW m-2 during plasma disruption, is expected to induce the shallow surface damages, such as melting, and even boiling of W/Cu monoblocks. Thus, the performance of damaged W/Cu monoblocks under subsequent long-term plasma discharges is a key concern that needs to be verified and tested on existing tokamaks. Since 2022, a new type of main limiter composed of ITER-like W/Cu monoblocks has been installed and tested in EAST. The surface of W/Cu monoblocks of the limiter was damaged by the transient heat flux during the early stages of plasma construction. Subsequently, they were subjected to long-term plasma discharges over 2600 shots in normal plasma discharge conditions. This circumstance conveniently facilitates the discussion of the performance of W/Cu monoblocks with damaged surfaces especially a melting edge with hill structure under prolonged exposure to plasma. In general, the shallow damage resulting from transient heat flux on W/Cu monoblocks appears to have minimal impact on the heat exhaust capacity under steady-state heat loads, as indicated by both experimental monitoring and numerical simulation results. However, shallow melting, leading to a change in surface structure and the formation of hills, could theoretically increase local temperatures, creating potential hot spots. This phenomenon requires further validation through dedicated experiments. Moreover, the brittleness of the near-surface layer may give rise to brittle destructions, such as cracks and even dust particles, posing an additional concern. These findings yield unique qualitative conclusions that can be referenced for ITER and other fusion devices. |
| WOS关键词 | FACING MATERIALS ; PERFORMANCE ; COMPONENTS ; BEHAVIOR ; TUNGSTEN ; DITTUS ; ARMOR |
| 资助项目 | the programs of National Natural Science Foundation of China[2022YFE03030000] ; the programs of National Natural Science Foundation of China[2022YFE0109700] ; National Key R&D Program of China[U21A20439] ; National Key R&D Program of China[12022511] ; National Key R&D Program of China[12205332,12205333] ; National Natural Science Foundation of China[2022HSC-CIP007] ; Collaborative Innovation Program of Hefei Science Center, CAS[ZDBS-LY-SLH010] ; Key Research Program of Frontier Sciences, CAS[2022AMF02002] ; Open Fund of Magnetic Confinement Fusion Laboratory of Anhui Province |
| WOS研究方向 | Physics |
| 语种 | 英语 |
| WOS记录号 | WOS:001248870700001 |
| 出版者 | IOP Publishing Ltd |
| 资助机构 | the programs of National Natural Science Foundation of China ; National Key R&D Program of China ; National Natural Science Foundation of China ; Collaborative Innovation Program of Hefei Science Center, CAS ; Key Research Program of Frontier Sciences, CAS ; Open Fund of Magnetic Confinement Fusion Laboratory of Anhui Province |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/136322]  |
| 专题 | 中国科学院合肥物质科学研究院 |
| 通讯作者 | Zhu, Dahuan; Wang, Baoguo |
| 作者单位 | 1.Univ Sci & Technol China, Sci Isl Branch, Grad Sch, Hefei 230021, Peoples R China 2.Chinese Acad Sci, Hefei Inst Phys Sci, Inst Plasma Phys, Hefei 230031, Peoples R China |
| 推荐引用方式 GB/T 7714 | Guo, Zongxiao,Zhu, Dahuan,Yan, Rong,et al. Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments[J]. NUCLEAR FUSION,2024,64. |
| APA | Guo, Zongxiao.,Zhu, Dahuan.,Yan, Rong.,Xuan, Chuannan.,Wang, Baoguo.,...&Chen, Junling.(2024).Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments.NUCLEAR FUSION,64. |
| MLA | Guo, Zongxiao,et al."Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments".NUCLEAR FUSION 64(2024). |
入库方式： OAI收割
来源：合肥物质科学研究院
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