Abstract Details

Divertors to enable tokamak fusion reactors

Author: Mike Kotschenreuther
Submitted: 2006-01-02 13:55:51

Co-authors: P. Valanju, S. Mahajan, J.C. Wiley

Contact Info:
Institute for Fusion Studies
1 University Station
Austin, TX   78712

Abstract Text:
We show that the relatively low thermal power (P) handling capacity of
conventional divertors forces extremely high (~ 95%) total radiation fractions
in fusion power reactors. Such radiation fraction has profound and deleterious
consequences on the core confinement and stability which implies that reactor
operation is very unlikely. These standard divertor limitations become serious
for power levels just beyond ITER-FEAT (400MW), which appears incapable of
operating in a mode which would extrapolate to a high power reactor. Even
Internal Transport Barriers are unlikley to provide a satisfactory solution.

By designing divertors with a considerably enhanced thermal capacity (through a
flaring of the field lines to increase plasma wetted area and line connection
length, or by extraction of the divertor filed lines to outside the TF coils)
we have proposed a divertor which appears likely allow a tokamak reactor. The
coils that we have designed for such divertor can be small additions (current
and cost) to the standard coil set. They enable a path to fusion power that
includes the necessary intermediate step of a low-cost Component Test Facility
(CTF) before building a reactor DEMO (which does not appear possible with
conventional divertors). We propose that they be tested on NSTX, PEGASUS and
other existing experiments.

Characterization: A5

Prefer oral talk. If not invited. please place with posters by Wiley, Valanju, Pekker

The University of Texas at Austin

Innovative Confinement Concepts Workshop
February 13-16, 2006
Austin, Texas

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