Lithium as a Plasma Facing Component to Optimize the Edge Plasma

被引：0
|
作者：
Maingi, R. [1 ]
Majeski, R. [1 ]
Menard, J. E. [1 ]
Jaworski, M. A. [1 ]
Kaita, R. [1 ]
机构：
[1] Princeton Plasma Phys Lab, POB 451, Princeton, NJ 08543 USA
来源：
2015 IEEE 26TH SYMPOSIUM ON FUSION ENGINEERING (SOFE) | 2015年
关键词：
plasma facing components; impurities; lithium; energy confinement; power exhaust; ITER; DIVERTOR; TOKAMAK; REGIME;
D O I：
暂无
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The use of lithium to coat plasma-facing components (PFCs) or serve directly as liquid PFCs has resulted in energy confinement improvement in several devices. Coupled with the demonstrated ability of liquid Li to exhaust high power fluxes, the use of Li could resolve the two leading problems of high-Z PFCs. The effect of Li in NSTX, EAST, and DIII-D is compared, and common features are identified. A compact spherical tokamak-based Fusion Nuclear Science Facility design could deliver an attractive neutral wall loading for materials testing, with Li PFCs enabling access to the required high confinement scenarios.
引用
收藏
页数：5
相关论文
共 50 条
  • [41] Design modification of plasma facing component and cassette body for ITER divertor
    Mazzone, G
    Lucca, F
    Mainardi, E
    Marin, A
    Merola, M
    Petrizzi, L
    Pizzuto, A
    Roccella, M
    Zanotelli, G
    20TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, PROCEEDINGS, 2003, : 100 - 105
  • [42] A review of lithium application for the plasma-facing material in EAST Tokamak
    Hu, J. S.
    Li, L.
    Zuo, G. Z.
    Sun, Z.
    Xu, W.
    Meng, X. C.
    Li, C. L.
    Tang, Z. L.
    Sun, J. Z.
    REVIEWS OF MODERN PLASMA PHYSICS, 2023, 7 (01)
  • [43] Protection of tokamak plasma facing components by a capillary porous system with lithium
    Lyublinski, I.
    Vertkov, A.
    Mirnov, S.
    Lazarev, V.
    JOURNAL OF NUCLEAR MATERIALS, 2015, 463 : 1156 - 1159
  • [44] PLASMA FACING MATERIALS
    GAUSTER, WB
    NUCLEAR FUSION, 1990, 30 (09) : 1897 - 1904
  • [45] Plasma facing materials
    Gauster, W.B., 1897, (30):
  • [46] Lithium coatings on NSTX plasma facing components and its effects on boundary control, core plasma performance, and operation
    Kugel, H. W.
    Bell, M. G.
    Schneider, H.
    Allain, J. P.
    Bell, R. E.
    Kaita, R.
    Kallman, J.
    Kaye, S.
    LeBlanc, B. P.
    Mansfield, D.
    Nygren, R. E.
    Maingi, R.
    Menard, J.
    Mueller, D.
    Ono, M.
    Paul, S.
    Gerhardt, S.
    Raman, R.
    Sabbagh, S.
    Skinner, C. H.
    Soukhanovskii, V.
    Timberlake, J.
    Zakharov, L. E.
    FUSION ENGINEERING AND DESIGN, 2010, 85 (06) : 865 - 873
  • [47] Numerical simulation of lithium granule injection in tokamak edge plasma
    Gao, Fang
    Sun, Jizhong
    Liu, Lijun
    Sun, Zhen
    Bonnin, Xavier
    Liu, Jinyuan
    AIP ADVANCES, 2019, 9 (01)
  • [48] The line emission of carbon and lithium beams in the plasma edge of TEXTOR
    Beigman, IL
    Kocsis, G
    Pospieszczyk, A
    Vainshtein, LA
    PLASMA PHYSICS AND CONTROLLED FUSION, 1998, 40 (10) : 1689 - 1705
  • [49] Numerical simulation of buoyant flow in a vertical channel for a plasma-facing component
    Satake, Shin-ichi
    Nagasawa, Hitoshi
    Imai, Ryunosuke
    FUSION ENGINEERING AND DESIGN, 2024, 202
  • [50] Progress in additive manufacturing of pure tungsten for plasma-facing component applications
    Mueller, A. V.
    Dorow-Gerspach, D.
    Balden, M.
    Binder, M.
    Buschmann, B.
    Curzadd, B.
    Loewenhoff, T.
    Neu, R.
    Schlick, G.
    You, J. H.
    JOURNAL OF NUCLEAR MATERIALS, 2022, 566
12345