Compatibility of divertor detachment and ELM suppression in DIII-D high- βp plasmas with ITER-similar shape
文献类型：期刊论文
| 作者 | Wu, D. G.2,3; Wang, L.2 ; Wang, H. Q.1; Garofalo, A. M.1; Gong, X. Z.2; Ding, S.1; Wang, Y. F.2; Lan, H.4; Yan, N.2; McClenaghan, J.1
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| 刊名 | NUCLEAR FUSION
 |
| 出版日期 | 2024-08-01 |
| 卷号 | 64 |
| 关键词 | high-beta(p) divertor detachment ELM suppression neon injection ITER-similar shape |
| ISSN号 | 0029-5515 |
| DOI | 10.1088/1741-4326/ad5852 |
| 通讯作者 | Wang, L.(lwang@ipp.ac.cn) ; Wang, H. Q.(wanghuiqian@fusion.gat.com) |
| 英文摘要 | Integration of transient and steady-state divertor heat fluxes control with a high-performance core is necessary for future fusion reactors. In recent DIII-D high- beta(p) experiments, divertor detachment and simultaneous edge localized mode (ELM) suppression are demonstrated while the plasma confinement quality is maintained high in ITER-similar shape. By optimizing the neon injection in high- beta(p) scenario with ITER-similar shape, deep detachment and ELM suppression are achieved with a high-performance core ( beta(N) similar to 2.8, beta(p) similar to 2.3) at q(95) similar to 7.5. Partial divertor detachment and suppression of large ELMs are achieved at q(95) similar to 6. The stability analyses suggest that with low neon injection, the density pedestal becomes higher and steeper and the T-i profile also increases, therefore the increased edge pressure and higher current density destabilize the Peeling-Ballooning mode (PBM), which would lead to a large ELM collapse. With strong neon gas puffing, the significantly reduced pedestal pressure and current density, due to the degraded T-e pedestal, lead to the stabilization of PBM and ELMs are suppressed. For both cases, the coupling between the large radius internal transport barrier (ITB) and edge pedestal is the key reason for maintaining high global performance. The formation of large radius ITB compensates for pedestal degradation. Such results could provide an attractive scenario to well control the transient and steady-state heat flux onto the divertor plates while maintaining good plasma performance, which is an important step toward the steady-state operation of future fusion reactors. |
| WOS关键词 | INTERNAL TRANSPORT BARRIER ; H-MODE ; CONFINEMENT ; STABILITY ; PEDESTAL ; PROGRESS ; PHYSICS ; SYSTEM |
| 资助项目 | National Natural Science Foundation of China[12275312] ; National Natural Science Foundation of China[11975275] ; National Natural Science Foundation of China[12105187] ; National MCF Energy RD Program[2022YFE03050000] ; U.S. Department of Energy[DE-FC02-04ER54698] ; U.S. Department of Energy[DE-AC52-07NA27344] ; HFIPS Director's Fund[BJPY2023A05] |
| WOS研究方向 | Physics |
| 语种 | 英语 |
| WOS记录号 | WOS:001260172900001 |
| 出版者 | IOP Publishing Ltd |
| 资助机构 | National Natural Science Foundation of China ; National MCF Energy RD Program ; U.S. Department of Energy ; HFIPS Director's Fund |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/136765]  |
| 专题 | 中国科学院合肥物质科学研究院 |
| 通讯作者 | Wang, L.; Wang, H. Q. |
| 作者单位 | 1.Gen Atom, POB 85608, San Diego, CA 92186 USA 2.Chinese Acad Sci, Hefei Inst Phys Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 3.Univ Sci & Technol China, Hefei 230026, Peoples R China 4.Southwest Jiaotong Univ, Sch Phys Sci & Technol, Inst Fus Sci, Chengdu 610031, Peoples R China 5.Lawrence Livermore Natl Lab, Livermore, CA 94550 USA |
| 推荐引用方式 GB/T 7714 | Wu, D. G.,Wang, L.,Wang, H. Q.,et al. Compatibility of divertor detachment and ELM suppression in DIII-D high- βp plasmas with ITER-similar shape[J]. NUCLEAR FUSION,2024,64. |
| APA | Wu, D. G..,Wang, L..,Wang, H. Q..,Garofalo, A. M..,Gong, X. Z..,...&Liu, J. B..(2024).Compatibility of divertor detachment and ELM suppression in DIII-D high- βp plasmas with ITER-similar shape.NUCLEAR FUSION,64. |
| MLA | Wu, D. G.,et al."Compatibility of divertor detachment and ELM suppression in DIII-D high- βp plasmas with ITER-similar shape".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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