An analysis of controlled detachment by seeding various impurity species in high performance scenarios on DIII-D and EAST

被引:34
作者
Eldon, D. [1 ]
Wang, H. Q. [1 ]
Wang, L. [2 ]
Barr, J. [1 ]
Ding, S. [5 ]
Garofalo, A. [1 ]
Gong, X. Z. [2 ]
Guo, H. Y. [1 ]
Jarvinen, A. E. [3 ]
Li, K. D. [2 ]
McClenaghan, J. [1 ]
McLean, A. G. [3 ]
Samuell, C. M. [3 ]
Watkins, J. G. [4 ]
Weisberg, D. [1 ]
Yuan, Q. P. [2 ]
机构
[1] Gen Atom, POB 85608, San Diego, CA 92186 USA
[2] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
[3] Lawrence Livermore Natl Lab, POB 808, Livermore, CA 94550 USA
[4] Sandia Natl Labs, POB 5800, Albuquerque, NM 87185 USA
[5] Oak Ridge Associated Univ, 100 ORAU Way, Oak Ridge, TN 37830 USA
基金
中国国家自然科学基金;
关键词
Plasma control; Detachment; Tokamak; Fusion; Divertor; HIGH CONFINEMENT; DIVERTOR; TRANSPORT;
D O I
10.1016/j.nme.2021.100963
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
Experiments at DIII-D and EAST have demonstrated simultaneous high confinement, divertor detachment, and active control of detachment level, all of which are required for ITER. Comparing detachment control via T-e and J(sat), it appears that T-e is the most straightforward sensor to use for accessing detachment onset, while J(sat) offers more precise control of degree of detachment. Based on these results, control using nitrogen seeding has so far shown the best ability to follow a target value with the low disruptivity and little to no degradation of performance when an Internal Transport Barrier (ITB) is present, but not all facilities allow its use. Neon seeding also can be paired with feedback control with low impact on core performance as long as there is no disruption, however shots with neon seeding commonly disrupted during these experiments. Argon is effective in EAST, but tends to degrade performance (by approximate to 10%beta(p)) when detachment is achieved. With ideal conditions and strike point position control, data from a single Langmuir probe are an acceptable input to the control algorithm, but this simple system is easily defeated by strike point displacement comparable to the T-e or J(sat) scale lengths. The presence of an ITB seems to be critical to retaining core performance in detachment in these parameter ranges, as the pedestal pressure tends to decrease as a result of impurity seeding.
引用
收藏
页数:10
相关论文
共 59 条
  • [1] Investigations of impurity seeding and radiation control for long-pulse and high-density H-mode plasmas in JT-60U
    Asakura, N.
    Nakano, T.
    Oyama, N.
    Sakamoto, T.
    Matsunaga, G.
    Itami, K.
    [J]. NUCLEAR FUSION, 2009, 49 (11)
  • [2] FAST GAS INJECTION SYSTEM FOR PLASMA PHYSICS EXPERIMENTS
    BATES, SC
    BURRELL, KH
    [J]. REVIEW OF SCIENTIFIC INSTRUMENTS, 1984, 55 (06) : 934 - 939
  • [3] Erosion, screening, and migration of tungsten in the JET divertor
    Brezinsek, S.
    Kirschner, A.
    Mayer, M.
    Baron-Wiechec, A.
    Borodkina, I
    Borodin, D.
    Coffey, I
    Coenen, J.
    den Harder, N.
    Eksaeva, A.
    Guillemaut, C.
    Heinola, K.
    Huber, A.
    Huber, V
    Imrisek, M.
    Jachmich, S.
    Pawelec, E.
    Rubel, M.
    Krat, S.
    Sergienko, G.
    Matthews, G. F.
    Meigs, A. G.
    Wiesen, S.
    Widdowson, A.
    Abduallev, S.
    Abhangi, M.
    Abreu, P.
    Afzal, M.
    Aggarwal, K. M.
    Ahlgren, T.
    Ahn, J. H.
    Aho-Mantila, L.
    Aiba, N.
    Airila, M.
    Albanese, R.
    Aldred, V.
    Alegre, D.
    Alessi, E.
    Aleynikov, P.
    Alfier, A.
    Alkseev, A.
    Allinson, M.
    Alper, B.
    Alves, E.
    Ambrosino, G.
    Ambrosino, R.
    Amicucci, L.
    Amosov, V.
    Sunden, E. Andersson
    Angelone, M.
    [J]. NUCLEAR FUSION, 2019, 59 (09)
  • [4] Surface heat flux feedback controlled impurity seeding experiments with Alcator C-Mod's high-Z vertical target plate divertor: performance, limitations and implications for fusion power reactors
    Brunner, D.
    Wolfe, S. M.
    LaBombard, B.
    Kuang, A. Q.
    Lipschultz, B.
    Reinke, M. L.
    Hubbard, A.
    Hughes, J.
    Mumgaard, R. T.
    Terry, J. L.
    Umansky, M. V.
    [J]. NUCLEAR FUSION, 2017, 57 (08)
  • [5] Modelling of nitrogen seeding experiments in the ASDEX Upgrade tokamak
    Casali, L.
    Fable, E.
    Dux, R.
    Ryter, F.
    [J]. PHYSICS OF PLASMAS, 2018, 25 (03)
  • [6] Thermal Analysis on Various Design Concepts of ITER Divertor Langmuir Probes
    Chen, L.
    Zhao, W.
    Zhong, G.
    Watts, C.
    Gunn, James P.
    Liu, X.
    Lian, Y.
    [J]. FUSION SCIENCE AND TECHNOLOGY, 2018, 73 (04) : 568 - 578
  • [7] Measurement of Radiated Power Loss on EAST
    Duan Yanmin
    Hu Liqun
    Mao Songtao
    Xu Ping
    Chen Kaiyun
    Lin Shiyao
    Zhong Guoqiang
    Zhang Jizong
    Zhang Ling
    Wang Liang
    [J]. PLASMA SCIENCE & TECHNOLOGY, 2011, 13 (05) : 546 - 549
  • [8] Advances in radiated power control at DIII-D
    Eldon, D.
    Kolemen, E.
    Humphreys, D. A.
    Hyatt, A. W.
    Jarvinen, A. E.
    Leonard, A. W.
    McLean, A. G.
    Moser, A. L.
    Petrie, T. W.
    Walker, M. L.
    [J]. NUCLEAR MATERIALS AND ENERGY, 2019, 18 : 285 - 290
  • [9] Controlling marginally detached divertor plasmas
    Eldon, D.
    Kolemen, E.
    Barton, J. L.
    Briesemeister, A. R.
    Humphreys, D. A.
    Leonard, A. W.
    Maingi, R.
    Makowski, M. A.
    McLean, A. G.
    Moser, A. L.
    Stangeby, P. C.
    [J]. NUCLEAR FUSION, 2017, 57 (06)
  • [10] Initial results of the high resolution edge Thomson scattering upgrade at DIII-D
    Eldon, D.
    Bray, B. D.
    Deterly, T. M.
    Liu, C.
    Watkins, M.
    Groebner, R. J.
    Leonard, A. W.
    Osborne, T. H.
    Snyder, P. B.
    Boivin, R. L.
    Tynan, G. R.
    [J]. REVIEW OF SCIENTIFIC INSTRUMENTS, 2012, 83 (10)