DIVERTOR PLATE POWER LOAD EQUALIZATION BY MEANS OF BIASING

被引：9

作者：

WEYNANTS, RR

机构：

来源：

PLASMA PHYSICS AND CONTROLLED FUSION | 1995年 / 37卷 / 02期

关键词：

D O I：

10.1088/0741-3335/37/2/001

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：

Biasing the scrape-off layer of a tokamak is discussed as a means of equalizing the power loads to and the recycling regimes in front of the target plates of a single null divertor. The scheme would be optimal with the grad-B drift directed towards the targets, thus ensuring a low H-mode threshold, and it might, at the same time, allow an increase in the wetted plate area. The electrical requirements for and development needs towards its application under ITER-like conditions are also discussed.

引用

页码：63 / 69

页数：7

共 24 条

[1] PLASMA-WALL TRANSITION IN AN OBLIQUE MAGNETIC-FIELD [J].

CHODURA, R .

PHYSICS OF FLUIDS, 1982, 25 (09) :1628-1633

[2]

CHOE W, 1992, P IAEA TECHNICAL C M, P297

[3]

DOERNER R, 1994, UNPUB NUCL FUSION

[4] BOUNDARY-LAYER CALCULATIONS FOR TOKAMAKS WITH TOROIDAL LIMITER [J].

GERHAUSER, H ;

CLAASSEN, HA .

JOURNAL OF NUCLEAR MATERIALS, 1990, 176 :721-728

[5]

HERMANN, 1993, 20TH P EPS C CONTR F, P567

[6]

JANESCHITZ G, 1993, 20TH P EPS C CONTR 2, P559

[7]

KRASHENINNIKOV SI, 1994, UNPUB PHYS PLASMAS

[8] PLASMA BIAS EXPERIMENTS ON TORTUS [J].

LI, XB ;

CROSS, RC ;

MILJAK, D .

PLASMA PHYSICS AND CONTROLLED FUSION, 1994, 36 (01) :73-79

[9]

MADHAVI MA, 1981, PHYS REV LETT, V47, P1602

[10]

MIODUSZEWSKI P, 1986, ADV LIMITERS PHYSICS, P891

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