Skip to main content
Log in

Magnetized Target Fusion with a Spherical Tokamak

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

Abstract

With good confinement and relatively high beta (up to 40%), the spherical tokamak could be a suitable magnetized target. To illustrate this potential, the theoretical fusion yield from compressing a spherical tokamak adiabatically to fusion conditions is calculated. While it is found that the large amount of energy stored in the compressed toroidal field constrains the potential energy gain, a system can be designed to produce significant useful output by directly recovering a large fraction of the compression energy. With 80% energy recovery, an example system using 140 MJ of pressurized gas to compress the spherical tokamak plasma within a 2 m radius liquid metal flux conserver can produce a fusion yield of 140 MJ and a net output of 40 MJ per pulse. At ~ 1 Hz this would produce 40 MWelectric.

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.

Fig. 1
Fig. 2

Similar content being viewed by others

References

  1. R.L. Miller, R.A. Krakowski, Assessment of the Slowly-Imploding Liner (LINUS) Fusion Reactor Concept, in 4th ANS Topical Meeting on the Technology of Nuclear Fusion (1980)

  2. P.J. Turchi, A.L. Cooper, R.D. Ford, D.J. Jenkins, R.L Burton, Review of the NRL Liner Implosion Program, in MegaGauss Physics and Technology (Plenum Press, New York, London, 1980), p. 375-386

  3. https://nstx.pppl.gov/accomplishments.html (2004)

  4. D.D. Ryutov, R.E. Siemon, Magnetized plasma configurations for fast liner implosions: a variety of possibilities. Comments Mod. Phys. 2C, 185–201 (2001)

    Google Scholar 

  5. T.R. Jarboe, Formation and steady-state sustainment of a tokamak by coaxial helicity injection. Fusion Technol. 15(1), 7–11 (1989)

    Article  Google Scholar 

  6. R. Siemon, I. Lindemuth, K. Schoenberg, Why magnetized target fusion offers a low-cost development path for fusion energy. Comments Plasma Phys. Controll. Fusion 18, 363–386 (1997)

    Google Scholar 

  7. M. Porkolab, High performance discharges and capabilities in alcator C-Mod. J. Fusion Energ. 15, 169 (1996). https://doi.org/10.1007/BF02266931

    Article  ADS  Google Scholar 

  8. M. Greenwald, Density limits in toroidal plasmas. Plasma Phys. Control. Fusion 44, R27 (2002)

    Article  ADS  Google Scholar 

  9. L.C. Bernard, F.J. Helton, R.W. Moore, T.N. Todd, MHD beta limits: scaling laws and comparison with Doublet III data. Nucl. Fusion 23, 1475 (1983)

    Article  Google Scholar 

  10. http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/16/028/16028204.pdf top of p.2

  11. R.J. La Haye et al., High beta tokamak operation in DIII-D limited at low density/collisionality by resistive tearing modes. Nucl. Fusion 37, 397 (1997)

    Article  ADS  Google Scholar 

  12. https://mcnp.lanl.gov/

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to Michel Laberge.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Laberge, M. Magnetized Target Fusion with a Spherical Tokamak. J Fusion Energ 38, 199–203 (2019). https://doi.org/10.1007/s10894-018-0180-3

Download citation

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10894-018-0180-3

Keywords

Navigation