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Advanced Divertors for Fusion

Author: Michael T Kotschenreuther
Requested Type: Consider for Invited
Submitted: 2012-12-07 15:21:20

Co-authors: B. Covele, P. M. Valanju, S. M. Mahajan

Contact Info:
Institute for Fusion Studies
University of Texas
Austin, Texas   78712
United States

Abstract Text:
The difficulty of power exhaust in Tokamaks becomes progressively more severe as fusion devices proceed through ITER, FNSF, DEMO and finally to a reactor. The problems are compounded by recent projections of Scrape-Off Layer (SOL )width, where the SOL becomes considerably narrower as the current is increased. The standard divertor is expected to become inadequate in the progression to a reactor. Novel solutions to exhaust problem have been developed, including the X-divertor, Snowflake divertor, and Super-X divertor, and we will compare them here. The magnetic feasibility of creating these configurations is considered, using free boundary equilibrium calculations from CORSICA. General features of the configurations will be compared, using analytical estimates and divertor plasma simulations using SOLPS. Finally, technologically important neutronic issues are compared, considering both divertor damage and the effect of the divertor geometry on adequacy of tritium breeding.

Characterization: 3.0


University of Texas

Workshop on Exploratory Topics in Plasma and Fusion Research (EPR2013)
February 12-15, 2013
Fort Worth, Texas

EPR 2013