The role of radial particle flow on power balance in DIII-D

被引:32
|
作者
Porter, GD [1 ]
机构
[1] Lawrence Livermore Natl Lab, Livermore, CA 94550 USA
[2] Gen Atom Co, La Jolla, CA 92037 USA
关键词
D O I
10.1063/1.873169
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
The importance of radial particle flow on the power flowing across the last closed flux surface (separatrix) in DIII-D et al., [Luxon et al., International Conference on Plasma Physics and Controlled Nuclear Fusion (International Atomic Energy Agency, Vienna, 1986), Vol. I, p. 159] is considered. The perpendicular thermal diffusivity at the separatrix is near 1 m(2)/s in low confinement operation (L-mode), and 0.1 m(2)/s in high confinement mode. The particle diffusivity is about one-fourth of the thermal diffusivity producing radial particle fluxes of the order of kilo-amperes. The particle flux is 10 to 100 times the particle input from neutral beam sources, consistent with core fueling being dominated by neutral recycling. The radial particle flux scales with the neutral pressure in the private flux region, suggesting the core is fueled predominantly from neutrals which recycle from the divertor, through the private flux, and into the core near the singular point where the poloidal field is zero (X- point). There is significant core power loss associated with the large particle flux across the separatrix. The electron temperature measured at the top of the edge pedestal in H-mode operation scales inversely with the particle flux. In turn, the core energy confinement scales with the pedestal temperature, and hence inversely with the particle flux. The results presented here indicate the global particle confinement time is between 0.5 and 2 times the global energy confinement time. (C) 1998 American Institute of Physics. [S1070-664X(98)03112-7].
引用
收藏
页码:4311 / 4320
页数:10
相关论文
共 50 条
  • [31] Divertor heat and particle control experiments on the DIII-D tokamak
    Mahdavi, M.A.
    Allen, S.L.
    Baker, D.R.
    Bastasz, B.
    Brooks, N.H.
    Buchenauer, D.
    Campbell, R.B.
    Cuthertson, J.W.
    Evans, T.E.
    Fenstemacher, M.E.
    Finkenthal, D.F.
    Foote, J.
    Hill, D.N.
    Hillis, D.L.
    Hinton, F.I.
    Hogan, J.
    Journal of Nuclear Materials, 1995, 220-222
  • [32] Effects of particle exhaust on neutral compression ratios in DIII-D
    Colchin, RJ
    Maingi, R
    Allen, SL
    Greenfield, CM
    Wade, MR
    JOURNAL OF NUCLEAR MATERIALS, 1999, 266 : 472 - 477
  • [33] Transport studies in DIII-D with modulated heat and particle sour
    DeBoo, JC
    Baker, DR
    Wade, MR
    FUSION SCIENCE AND TECHNOLOGY, 2005, 48 (02) : 988 - 996
  • [34] Parametric dependence of the edge radial electric field in the DIII-D tokamak
    Gohil, P
    Burrell, KH
    Carlstrom, TN
    NUCLEAR FUSION, 1998, 38 (01) : 93 - 102
  • [35] Experimental measurements of the particle flux and sheath power transmission factor profiles in the divertor of DIII-D
    Donovan, D.
    Buchenauer, D.
    Watkins, J.
    Leonard, A.
    Wong, C.
    Schaffer, M.
    Rudakov, D.
    Lasnier, C.
    Stangeby, P.
    JOURNAL OF NUCLEAR MATERIALS, 2013, 438 : S467 - S471
  • [36] Role of neutrals in density pedestal formation in DIII-D
    Groebner, RJ
    Mahdavi, MA
    Leonard, AW
    Osborne, TH
    Porter, GD
    PLASMA PHYSICS AND CONTROLLED FUSION, 2002, 44 : A265 - A272
  • [37] Thermal ion orbit loss and radial electric field in DIII-D
    degrassie, J. S.
    Boedo, J. A.
    Grierson, B. A.
    PHYSICS OF PLASMAS, 2015, 22 (08)
  • [38] Modeling of the recycling particle flux and electron particle transport in the DIII-D tokamak
    Baker, D.R
    Maingi, R.
    Owen, L.W.
    Porter, G.D.
    Jackson, G.L.
    Journal of Nuclear Materials, 241-243 : 602 - 605
  • [39] The role of thermal instabilities in limiting the density in DIII-D
    Stacey, WM
    Petrie, TW
    PHYSICS OF PLASMAS, 2000, 7 (12) : 4931 - 4941
  • [40] Modeling of the recycling particle flux and electron particle transport in the DIII-D Tokamak
    Baker, DR
    Maingi, R
    Owen, LW
    Porter, GD
    Jackson, GL
    JOURNAL OF NUCLEAR MATERIALS, 1997, 241 : 602 - 605