Prospects for toroidal fusion reactors

John Sheffield; John D. Galambos

doi:10.13182/fst94-a40304

Prospects for toroidal fusion reactors

John Sheffield, John D. Galambos

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Abstract

Work on the International Thermonuclear Experimental Reactor (ITER) tokamak has refined understanding of the realities of a deuterium-tritium (D-T) burning magnetic fusion reactor. An ITER-like tokamak reactor using ITER costs and performance would lead to a cost of electricity (COE) of about 130 mills/kWh. Advanced tokamak physics to be tested in the Toroidal Physics Experiment (TPX), coupled with moderate extrapolation in engineering, technology, and unit costs (i.e., based on the ITER design), should lead to a COE comparable with best existing fission systems around 60 mills/kWh. However, a larger unit size, approx.2000 MW_(e), is favored for the fusion system. Alternative toroidal configurations to the conventional tokamak, such as the stellarator, reversed-field pinch, and field-reversed configuration, offer some potential advantage, but are less well developed, and have their own challenges.

Original language	English
Pages (from-to)	1122-1126
Number of pages	5
Journal	Fusion Technology
Volume	26
Issue number	3 pt 2
DOIs	https://doi.org/10.13182/fst94-a40304
State	Published - 1994
Event	Proceedings of the 11th Topical Meeting on the Technology of Fusion Energy - New Orleans, LA, USA Duration: Jun 19 1994 → Jun 23 1994

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abstract = "Work on the International Thermonuclear Experimental Reactor (ITER) tokamak has refined understanding of the realities of a deuterium-tritium (D-T) burning magnetic fusion reactor. An ITER-like tokamak reactor using ITER costs and performance would lead to a cost of electricity (COE) of about 130 mills/kWh. Advanced tokamak physics to be tested in the Toroidal Physics Experiment (TPX), coupled with moderate extrapolation in engineering, technology, and unit costs (i.e., based on the ITER design), should lead to a COE comparable with best existing fission systems around 60 mills/kWh. However, a larger unit size, approx.2000 MW(e), is favored for the fusion system. Alternative toroidal configurations to the conventional tokamak, such as the stellarator, reversed-field pinch, and field-reversed configuration, offer some potential advantage, but are less well developed, and have their own challenges.",

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AU - Sheffield, John

AU - Galambos, John D.

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N2 - Work on the International Thermonuclear Experimental Reactor (ITER) tokamak has refined understanding of the realities of a deuterium-tritium (D-T) burning magnetic fusion reactor. An ITER-like tokamak reactor using ITER costs and performance would lead to a cost of electricity (COE) of about 130 mills/kWh. Advanced tokamak physics to be tested in the Toroidal Physics Experiment (TPX), coupled with moderate extrapolation in engineering, technology, and unit costs (i.e., based on the ITER design), should lead to a COE comparable with best existing fission systems around 60 mills/kWh. However, a larger unit size, approx.2000 MW(e), is favored for the fusion system. Alternative toroidal configurations to the conventional tokamak, such as the stellarator, reversed-field pinch, and field-reversed configuration, offer some potential advantage, but are less well developed, and have their own challenges.

AB - Work on the International Thermonuclear Experimental Reactor (ITER) tokamak has refined understanding of the realities of a deuterium-tritium (D-T) burning magnetic fusion reactor. An ITER-like tokamak reactor using ITER costs and performance would lead to a cost of electricity (COE) of about 130 mills/kWh. Advanced tokamak physics to be tested in the Toroidal Physics Experiment (TPX), coupled with moderate extrapolation in engineering, technology, and unit costs (i.e., based on the ITER design), should lead to a COE comparable with best existing fission systems around 60 mills/kWh. However, a larger unit size, approx.2000 MW(e), is favored for the fusion system. Alternative toroidal configurations to the conventional tokamak, such as the stellarator, reversed-field pinch, and field-reversed configuration, offer some potential advantage, but are less well developed, and have their own challenges.

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Prospects for toroidal fusion reactors

Abstract

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