Evaluation of edge transport and core accumulation of tungsten for CFETR with EMC3-EIRENE and STRAHL
文献类型：期刊论文
| 作者 | Liu, B.2 ; Dai, S. Y.2; Yang, X. D.3; Chan, V. S.1; Ding, R.3; Zhang, H. M.3; Feng, Y.4; Wang, D. Z.2
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| 刊名 | NUCLEAR FUSION
 |
| 出版日期 | 2022-12-01 |
| 卷号 | 62 |
| ISSN号 | 0029-5515 |
| 关键词 | tungsten distribution CFETR EMC3-EIRENE STRAHL |
| DOI | 10.1088/1741-4326/ac95aa |
| 通讯作者 | Dai, S. Y.(daishuyu@dlut.edu.cn) |
| 英文摘要 | The edge transport and core accumulation of tungsten (W) particles on China Fusion Engineering Test Reactor (CFETR) have been studied by integrated modelling consisting of EMC3-EIRENE and STRAHL codes. The edge transport and power dissipation of W particles are simulated by EMC3-EIRENE. An in-out asymmetry of W(1-28)+ ions density has been revealed in the in- and out-board divertor regions. This is mainly due to the stronger reversal flow velocity of W ions at the outboard divertor. The upward flow of W ions near the separatrix leads to a moderate W impurity leakage from the divertor on CFETR compared to the existing full W device ASDEX Upgrade due to the high plasma density near the CFETR divertor targets. Further, the density distribution and radiation loss of W ions in the core region are investigated by STRAHL code. The high charge-state W(29-60)+ and W(61-74)+ ions mainly reside in the regions of psi(N) = 0.20-0.98 and 0.00-0.90 (psi(N) is the normalized poloidal magnetic flux), respectively. The W induced energy dissipation in different regions is assessed according to both STRAHL and EMC3-EIRENE simulations. Particularly, the impacts of the W core radiation on the operation regime are discussed according to the H-mode threshold scaling law proposed by Martin et al (2008 J. Phys.: Conf. Ser. 123 012033) for the baseline plasma on CFETR. Further, parameter studies on the pinch velocity (v (imp)) and diffusion coefficient (D (imp)) have been performed to check their impacts on the operation regime of CFETR. A three-fold increase of v (imp)/D (imp) results in a higher W core energy loss, which can lead to the transition from H-mode back to L-mode. |
| WOS关键词 | ISLAND DIVERTORS ; PHYSICS ; PLASMA ; ITER |
| 资助项目 | National MCF Energy R&D Program of China[2018YFE0311100] ; National MCF Energy R&D Program of China[2018YFE0303105] ; National Natural Science Foundation of China[12075047] ; Fundamental Research Funds for the Central Universities[DUT21LK05] |
| WOS研究方向 | Physics |
| 语种 | 英语 |
| 出版者 | IOP Publishing Ltd |
| WOS记录号 | WOS:000870862000001 |
| 资助机构 | National MCF Energy R&D Program of China ; National Natural Science Foundation of China ; Fundamental Research Funds for the Central Universities |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/129462]  |
| 专题 | 中国科学院合肥物质科学研究院 |
| 通讯作者 | Dai, S. Y. |
| 作者单位 | 1.Univ Sci & Technol China, Sch Phys Sci, Dept Engn & Appl Phys, Hefei 230031, Anhui, Peoples R China 2.Dalian Univ Technol, Key Lab Mat Modificat Laser Ion & Electron Beams, Minist Educ, Sch Phys, Dalian 116024, Peoples R China 3.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 4.Max Planck Inst Plasma Phys, D-17491 Greifswald, Germany |
| 推荐引用方式 GB/T 7714 | Liu, B.,Dai, S. Y.,Yang, X. D.,et al. Evaluation of edge transport and core accumulation of tungsten for CFETR with EMC3-EIRENE and STRAHL[J]. NUCLEAR FUSION,2022,62. |
| APA | Liu, B..,Dai, S. Y..,Yang, X. D..,Chan, V. S..,Ding, R..,...&Wang, D. Z..(2022).Evaluation of edge transport and core accumulation of tungsten for CFETR with EMC3-EIRENE and STRAHL.NUCLEAR FUSION,62. |
| MLA | Liu, B.,et al."Evaluation of edge transport and core accumulation of tungsten for CFETR with EMC3-EIRENE and STRAHL".NUCLEAR FUSION 62(2022). |
入库方式： OAI收割
来源：合肥物质科学研究院
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