Skip to main content
Log in

The design of the Tokamak Physics Experiment (TPX)

  • Published:
Journal of Fusion Energy Aims and scope Submit manuscript

Abstract

The Tokamak Physics Experiment is designed to develop the scientific basis for a compact and continuously operating tokamak fusion reactor. It is based on an emerging class of tokamak operating modes, characterized by beta limits well in excess of the Troyon limit, confinement scaling well in excess of H-mode, and bootstrap current fractions approaching unity. Such modes are attainable through the use of advanced, steady state plasma controls including strong shaping, current profile control, and active particle recycling control. Key design features of the TPX are superconducting toroidal and poloidal field coils; actively-cooled plasma-facing components; a flexible heating and current drive system; and a spacious divertor for flexibility. Substantial deuterium plasma operation is made possible with an in-vessel remote maintenance system, a lowactivation titanium vacuum vessel, and shielding of ex-vessel components. The facility will be constructed as a national project with substantial participation by U.S. industry. Operation will begin with first plasma in the year 2000.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Similar content being viewed by others

References

  1. E. A. Lazarus, and the DIII-D Team. Dependence of β·τ on plasma shape in DIII-D. Presented at 20th EPS Conference on Controlled Fusion and Plasma Physics, July 26–30, 1993, Lisboa, Portugal. To be published inProceedings.

  2. F. Najmabadi,et al. (1991). IAEA Würzburg, Germany, 1992/Paper G-1-1-1(R); J. Wesleyet al. (1991). IAEA Würzburg, Germany, 1992/Paper F-1-2; Y. Sekiet al. (1991). Rep. JAERI-M 91-081, JAERI, Naka.

  3. N. Inoue,et al. (1992). IAEA Würzburg, Germany, Paper G-1-4.

  4. S. Texter,et al. (1993).Phys. Lett. A 175, 428; R. Kaita,et al. (1992). IAEA Würzburg, Germany, PBX-M post-deadline paper.

    Google Scholar 

  5. M. Kikuchi, (1990).Nucl. Fusion 30, 265; R. W. Conn, F. Najmabadiet al. (1990). ARIES-I, A Steady-State First-Stability Tokamak Reactor with Enhanced Safety and Environmental Features. 13th Int. Conf. on Plasma Physics and Controlled Nuclear Fusion Research, Washington, D.C., October 1–6, Paper IAEA-CN-53/H-1-4.

    Google Scholar 

  6. N. A. Uckan,et al. (1990). ITER Physics Design Guidelines: 1989, ITER Documentation Series No. 10, IAEA, Vienna.

    Google Scholar 

  7. R. J. LaHaye, A. W. Hyatt, and J. T. Scoville (1992). Non-Linear Instability to Lowm, n=1 Error Fields in DIII-D as a Function of Plasma Fluid Rotation and Beta. General Atomics Report GA-A20824, May, to be published inNucl. Fusion.

  8. T. Petrie,et al. (1992). Divertor heat flux reduction by D2 injection in DIII-D.Bull. Am. Phys. Soc. 37, 1565 (abstract).

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Rights and permissions

Reprints and permissions

About this article

Cite this article

Schmidt, J.A., Thomassen, K.I., Goldston, R.J. et al. The design of the Tokamak Physics Experiment (TPX). J Fusion Energ 12, 221–258 (1993). https://doi.org/10.1007/BF01079667

Download citation

  • Issue Date:

  • DOI: https://doi.org/10.1007/BF01079667

Keywords

Navigation