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5 - Design of a simple magnetic fusion reactor

Published online by Cambridge University Press:  14 May 2010

Jeffrey P. Freidberg
Affiliation:
Massachusetts Institute of Technology
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Summary

Introduction

Power balance considerations have shown that a magnetic fusion reactor should operate at a temperature of about 15 keV and be designed to achieve a value of pτE > 8.3 atm s. Even so, these considerations do not shed any light on the optimum tradeoff between p and τE. Nor do they provide any insight into the geometric scale and magnetic field of a fusion reactor. This is the goal of Chapter 5, which presents the design of a simple magnetic fusion reactor. All geometric and magnetic quantities are calculated as well as the critical plasma physics parameters.

Remarkably, the design requires virtually no knowledge of plasma physics even though for nearly half a century the field has been dominated by the study of this new branch of science. The design is actually driven largely by basic engineering and nuclear physics constraints. These constraints determine the geometric scale of the reactor as well as the size of the magnetic field. Equally important, they make “demands” on the plasma parameters. Plasma physicists must learn how to create plasmas that satisfy these demands (e.g. pressure and confinement time) in order for fusion to become a commercially viable source of energy. Knowledge of the desired plasma parameters is crucial as it defines the end goals of fusion-related plasma physics research, and serves as the guiding motivation for essentially all of the discussion of plasma physics in the remainder of the book.

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Chapter
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Publisher: Cambridge University Press
Print publication year: 2007

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References

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Gross, R. (1984). Fusion Energy. New York: John Wiley & Sons.Google Scholar
Rose, D. J. and Clark, M. (1961). Plasmas and Controlled Fusion. Cambridge, Massachusetts: MIT Press.Google Scholar
Stacey, W. M. (1981). Fusion Plasma Analysis. New York: John Wiley & Sons.Google Scholar
Stacey, W. M. (2005). Fusion Plasma Physics. Weinheim: Wiley-VCH.CrossRefGoogle Scholar
Badger, B., Abdou, M. A., et al. (1974). UWMAK-I – A Wisconsin Toroidal Fusion Reactor Design, UWFDM-68, University of Wisconsin Report. Madison Wisconsin: University of Wisconsin.Google Scholar
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ITER Team (2002). ITER Technical Basis. ITER EDA Documentation Series Number 24. Vienna: IAEA.
Maisonnier, D., Cook, L., et al. (2005). A Conceptual Study of Commercial Fusion Power Plants, EFDA-RP-RE-5.0, EFDA Report.Google Scholar
Meade, D. M. (2000). Mission and design of the Fusion Ignition Research Experiment (FIRE), Proceedings of the Eighteenth IAEA International Conference on Fusion Energy, Sorrento, Italy. Vienna: IAEA.CrossRefGoogle Scholar
Najmabadi, F., Conn, R. W., et al. (1991). The Aries-I Tokamak Fusion Reactor Study. Fusion Technology, p. 253 Amsterdam: North Holland.Google Scholar
Najmabadi, F. and the ARIES Team (1997). Overview of the ARIES-RS Reverse-Shear Tokamak Power Plant Study, Fusion Engineering and Design Vol 38, p. 3. Amsterdam, North Holland.Google Scholar
Najmabadi, F.Jardin, S. C.et al. (2000). ARIES-AT: An advanced Tokamak, advanced technology fusion power plant, Proceedings of the Eighteenth IAEA International Conference on Fusion Energy, Sorrento, Italy. Vienna: IAEA.Google Scholar
Dolan, T. J. (1982). Fusion Research. New York: Pergamon Press.Google Scholar
Gross, R. (1984). Fusion Energy. New York: John Wiley & Sons.Google Scholar
Rose, D. J. and Clark, M. (1961). Plasmas and Controlled Fusion. Cambridge, Massachusetts: MIT Press.Google Scholar
Stacey, W. M. (1981). Fusion Plasma Analysis. New York: John Wiley & Sons.Google Scholar
Stacey, W. M. (2005). Fusion Plasma Physics. Weinheim: Wiley-VCH.CrossRefGoogle Scholar
Badger, B., Abdou, M. A., et al. (1974). UWMAK-I – A Wisconsin Toroidal Fusion Reactor Design, UWFDM-68, University of Wisconsin Report. Madison Wisconsin: University of Wisconsin.Google Scholar
Coppi, B., Airoldi, A., Bombarda, F., Cenacchi, G., Defragiache, P., and Sugiyama, L. E. (2001). Optimal regimes for ignition and the Ignitor Experiment, Nuclear Fusion 41, 1253.CrossRefGoogle Scholar
ITER Team (2002). ITER Technical Basis. ITER EDA Documentation Series Number 24. Vienna: IAEA.
Maisonnier, D., Cook, L., et al. (2005). A Conceptual Study of Commercial Fusion Power Plants, EFDA-RP-RE-5.0, EFDA Report.Google Scholar
Meade, D. M. (2000). Mission and design of the Fusion Ignition Research Experiment (FIRE), Proceedings of the Eighteenth IAEA International Conference on Fusion Energy, Sorrento, Italy. Vienna: IAEA.CrossRefGoogle Scholar
Najmabadi, F., Conn, R. W., et al. (1991). The Aries-I Tokamak Fusion Reactor Study. Fusion Technology, p. 253 Amsterdam: North Holland.Google Scholar
Najmabadi, F. and the ARIES Team (1997). Overview of the ARIES-RS Reverse-Shear Tokamak Power Plant Study, Fusion Engineering and Design Vol 38, p. 3. Amsterdam, North Holland.Google Scholar
Najmabadi, F.Jardin, S. C.et al. (2000). ARIES-AT: An advanced Tokamak, advanced technology fusion power plant, Proceedings of the Eighteenth IAEA International Conference on Fusion Energy, Sorrento, Italy. Vienna: IAEA.Google Scholar

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