Control of tungsten impurity source and edge transport using different gas injection with full tungsten divertor on EAST | |
Ding, R.1; Xu, G. L.1; Wang, H.1; Ding, F.1; Zhang, L.1; Zhang, Q.1; Li, K. D.1; Liu, J. B.1; Brezinsek, S.2; Kirschner, A.2 | |
刊名 | NUCLEAR MATERIALS AND ENERGY |
2022-10-01 | |
卷号 | 33 |
DOI | 10.1016/j.nme.2022.101250 |
通讯作者 | Ding, R.(rding@ipp.ac.cn) ; Xu, G. L.(guoliang.xu@ipp.ac.cn) |
英文摘要 | Tungsten (W) erosion and edge transport are investigated for EAST L-mode discharges with different gas injection. It is found that W erosion can be suppressed or mitigated by Ne or D-2 seeding when divertor detachment is achieved. Compared to edge D-2 fueling, Ne seeding from the divertor target is favorable for full detachment condition and thus W erosion suppression. Increasing the upstream plasma density by edge D-2 fueling can affect the divertor condition, which may lead to a W erosion mitigation. D-2 puffing at divertor target is less effective on increasing the upstream plasma density than OMP D-2 puffing, and thus it is less effective on reduction of W erosion rates. W gross erosion profiles with different amount of injected D-2 at the divertor are reproduced by a mixed material W erosion model, which indicates that there exist a Li-C overlayer on the W surface of EAST divertor. Ne and D-2 injection are also found to have different impact on the normalized core W density. For the attached divertor condition, divertor Ne seeding will increase W leakage, but a suitable D-2 fueling from divertor target can strengthen the edge W screening. After the divertor detachment, although the W source is dramatically reduced, the W core density is kept in a high level for the Ne seeding discharges, and even increased for the D-2 fueling discharges. |
资助项目 | National Natural Science Foundation of China[12022511] ; National Natural Science Foundation of China[12005143] ; National Key Research and Development Program of China ; National MCF Energy R&D Program of China[2022YFE03180100] ; National MCF Energy R&D Program of China[2019YFE03080100] ; Key Research Program of Frontier Sciences, CAS[ZDBS-LY-SLH010] ; Science Foundation of Institute of Plasma Physics, Chinese Academy of Sciences[DSJJ-2021-02] |
WOS关键词 | LITHIUM ; EROSION |
WOS研究方向 | Nuclear Science & Technology |
语种 | 英语 |
出版者 | ELSEVIER |
WOS记录号 | WOS:000862873900008 |
资助机构 | National Natural Science Foundation of China ; National Key Research and Development Program of China ; National MCF Energy R&D Program of China ; Key Research Program of Frontier Sciences, CAS ; Science Foundation of Institute of Plasma Physics, Chinese Academy of Sciences |
内容类型 | 期刊论文 |
源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/129277] |
专题 | 中国科学院合肥物质科学研究院 |
通讯作者 | Ding, R.; Xu, G. L. |
作者单位 | 1.Chinese Acad Sci, Inst Plasma Phys, Hefei, Peoples R China 2.Forschungszentrum Julich, Inst Energie & Klimaforsch, Julich, Germany |
推荐引用方式 GB/T 7714 | Ding, R.,Xu, G. L.,Wang, H.,et al. Control of tungsten impurity source and edge transport using different gas injection with full tungsten divertor on EAST[J]. NUCLEAR MATERIALS AND ENERGY,2022,33. |
APA | Ding, R..,Xu, G. L..,Wang, H..,Ding, F..,Zhang, L..,...&Chen, J. L..(2022).Control of tungsten impurity source and edge transport using different gas injection with full tungsten divertor on EAST.NUCLEAR MATERIALS AND ENERGY,33. |
MLA | Ding, R.,et al."Control of tungsten impurity source and edge transport using different gas injection with full tungsten divertor on EAST".NUCLEAR MATERIALS AND ENERGY 33(2022). |
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