Low-Temperature Plasma Near a Tokamak Reactor Limiter

Abstract

Analytic and two-dimensional computational solutions for the plasma parameters near a toroidally synnetric limiter are illustrated for the projected parameters of a Tokamak Fusion Core Experiment {TFCX). The temperature near the limiter plate is belo* 20 eV, except when the density 10 cm inside the limiter contact is 8 x 10' 3 cm~3 or less and the thermal diffusivity in the edge region is 2 x 10*cin 2 /s or less. Extrapolation of recent experimental data suggests that neither of these conditions is likely to be met near ignition in TFCX, 30 a low plasma temperature near the limiter should be considered a likely possibility. DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United Stales Government. Nether the United States Government nor any agency thereof, nor any or he* hZ^r.V!!' "? Wa " a '! ,y • eXPr05S " iraplicd ' °r assum « »* '^1 liability or responsi bly for the accuracy, completeness, or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights Reference ce here,n to any spec.no commercial product, process, or service by trade name, trademark, • ll.v ' ? "T ^, nM """"* Mns,i,u " ! m in ""y its endorsement, rrW mendauon, or favoring by the United Stales Government or any a R ency thereof. The Views UdtSLr " " MPrKSed herei " d° " 0t nKCSSariIy 5,a "<>' ""«' tho= 0 ' be United States Government or anv agency thereof. F.O.H. Instituut voor Plasmafysica, Bieuwegein, The Netherlands. MASTER mmurm OF res n»ar is m&

Numerical analysis of the SOL/divertor plasma flow with the effect of drifts

“…(Henceforth, abbreviation 'HMAD' will be used for such high Mach flows associated with the detachment.) Recently, numerical simulation using B2-Eirene SOLPS 4.0 code [3][4][5] has been done to clarify the physical mechanism of the HMAD [6,7]. In addition, effects of E · B and diamagnetic drifts on the HMAD have been studied by using B2.5-Eirene SOLPS 5.0 code [8][9][10] in Refs.…”

Benchmarking Tokamak edge modelling codes

“…The codes currently being compared are SOLPS ("B2.5-Eirene") [1][2][3][4][5], EDGE2D-NIMBUS [6][7][8][9] and EDGE2D-EIRENE, all with Monte-Carlo neutrals; and SOLPS ("B2.5") [10][11][12][13][14][15] and UEDGE [16], with fluid neutrals. In order to remove one possible source of differences in the codes, all of the codes are using the same grid (the standard grid generated by the JET GRID2D [6] or, for some test cases, an orthogonal grid generated by UEDGE).…”

Effect of drifts on the high Mach flow associated with the divertor detachment

“…Large Mach flows up to Mach 1 or even larger have been measured near the X-point away from the target plate in these experiments (Henceforth, abbreviation ÔHMADÕ will be used for such high Mach flows associated with the detachment state). Recently, a numerical simulation using B2-EIRENE code [3][4][5] has been done to clarify the physical mechanism of HMAD [6]. In addition, comparison of numerical results with experiments in JT-60U has been done, and the effects of divertor geometry on HMAD were also studied [7].…”