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Toroidal equilibrium analysis of poloidal divertor RFP

Journal Article · · Fusion Technology
OSTI ID:219784
 [1];  [2]
  1. Saitama Univ. (Japan)
  2. Tokyo Inst. of Technology (Japan)
A toroidal equilibrium of a poloidal divertor RFP is analyzed as a free boundary problem including an external coil current of a vertical field and a poloidal divertor. Effects of poloidal divertor upon equilibrium parameter of RFP and the proximity of plasma to the conducting shell are investigated and the poloidal divertor configuration is shown to decrease the proximity of plasma to the shell to the value, [r{sub p}]/a{sub w}<=0.75, and be high {Theta} RFP without additional plasma surface controls. 6 refs., 5 figs.
OSTI ID:
219784
Report Number(s):
CONF-941182--
Journal Information:
Fusion Technology, Journal Name: Fusion Technology Vol. 27; ISSN 0748-1896; ISSN FUSTE8
Country of Publication:
United States
Language:
English