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Analysis of the Key Features of the Demountable Tokamak Fusion Core Concept

S. Locke Bogart, John A. Dalessandro (EASI), Peter Koert (IRT), Thomas J. Seed (LANL), Daniel L. Vrable (GAT), Carl E. Wagner (TRW), Carl F. Weggel (EASI)

Fusion Science and Technology / Volume 8 / Number 1P2B / July 1985 / Pages 1339-1344

Next-Generation Device / Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) / dx.doi.org/10.13182/FST85-A39954

The Demountable Tokamak Fusion Core (DTFC) concept is a water-cooled, normally conducting tokamak provided with joints in the toroidal field coil turns. These joints, located in the top and bottom horizontal members of each turn, permit the removal and replacement of the core of the tokamak (central OH coil, vacuum vessel, impurity control system, RF heating and current drive systems, inner blanket, and PF trimming coils). The rest of the tokamak (outer blanket, toroidal field current return coils, and main PF coils) remains in-place. This feature arises because the DTFC was conceived in recognition of the fact the core of the tokamak is directly exposed to fusion neutron and charged particle radiation and is the subsystem that will fail first. Provision for the replacement of the core in a straightforward way will significantly increase the availability of a DTFC facility for engineering and commercial applications.