Simulation of impurity behaviour in Experimental Advanced Superconducting Tokamak L-mode discharges with the integrated COREDIV code | |
Xie, H.1,2; Zagorski, R.3; Ding, R.1; Ivanova-Stanik, I.3; Chen, J. L.1; Zang, Q.1; Duan, Y. M.1; Zhang, H. M.1; Lyu, B.1; Chen, Y. J.1 | |
刊名 | CONTRIBUTIONS TO PLASMA PHYSICS |
2018-07-01 | |
卷号 | 58期号:6-8页码:765-772 |
关键词 | COREDIV EAST tokamak impurity transport modelling |
ISSN号 | 0863-1042 |
DOI | 10.1002/ctpp.201700130 |
通讯作者 | Ding, R.(rding@ipp.ac.cn) |
英文摘要 | The self-consistent COREDIV code has been used to simulate the Experimental Advanced Superconducting Tokamak (EAST) L-mode discharges of upper and lower single null configurations operated with tungsten and carbon divertors, respectively. In the simulations, a uniform lithium injection (and, in addition, a C injection for W divertor) from the wall is assumed, and calculations are performed for different diffusion coefficients in the Scrape-Off Layer (SOL) region. Simulations demonstrate that, in the case with C target, higher lithium flux leads to lower sputtered carbon flux because of the lower particle flux to divertor due to the plasma dilution by lithium. For the case of tungsten target, lithium has almost no influence on plasma parameters. Carbon seeding first leads to higher W concentrations and then to saturated W afterwards. The effect of a prompt re-deposition process is moderate due to the self-regulated increase of plasma temperature at the target through tungsten radiation in the core plasma. The simulations can well reproduce the experimental measurements such as plasma density and temperature profiles in the core region, Z(eff), total radiation loss and radiation profiles, and electron density and temperature profiles along divertor target. |
资助项目 | H2020 Euratom[633053] ; National Key Research and Development Program of China[2017YFA0402500] ; National Nature Science Foundation of China[11375010] ; National Nature Science Foundation of China[11675218] ; CASHIPS Directors Funds[YZJJ201612] |
WOS关键词 | ITER-LIKE WALL |
WOS研究方向 | Physics |
语种 | 英语 |
出版者 | WILEY-V C H VERLAG GMBH |
WOS记录号 | WOS:000443937100049 |
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内容类型 | 期刊论文 |
源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/38719] |
专题 | 合肥物质科学研究院_中科院等离子体物理研究所 |
通讯作者 | Ding, R. |
作者单位 | 1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China 2.Shenzhen Univ, Coll Optoelect Engn, Minist Educ & Guangdong Prov, Key Lab Optoelect Devices & Syst, Shenzhen, Peoples R China 3.Inst Plasma Phys & Laser Microfus, Warsaw, Poland |
推荐引用方式 GB/T 7714 | Xie, H.,Zagorski, R.,Ding, R.,et al. Simulation of impurity behaviour in Experimental Advanced Superconducting Tokamak L-mode discharges with the integrated COREDIV code[J]. CONTRIBUTIONS TO PLASMA PHYSICS,2018,58(6-8):765-772. |
APA | Xie, H..,Zagorski, R..,Ding, R..,Ivanova-Stanik, I..,Chen, J. L..,...&Feng, W..(2018).Simulation of impurity behaviour in Experimental Advanced Superconducting Tokamak L-mode discharges with the integrated COREDIV code.CONTRIBUTIONS TO PLASMA PHYSICS,58(6-8),765-772. |
MLA | Xie, H.,et al."Simulation of impurity behaviour in Experimental Advanced Superconducting Tokamak L-mode discharges with the integrated COREDIV code".CONTRIBUTIONS TO PLASMA PHYSICS 58.6-8(2018):765-772. |
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