Plasma Design Considerations of Near Term Tokamak Fusion Experimental Reactor

Masayoshi Sugihara, Nobol Fujisawa, Ryuichi Shimada, Kojyu Ueda, Seiji Saito, Akiyoshi Hatayama

Research output: Contribution to journalArticle

Abstract

Wide range of parameter surveys are made on the DT fusion tokamak experimental reactor next to JT-60. Various physics and engineering requirements are taken into account, e.g. self-ignition, available maximum toroidal β value, α-particle confinement, total fusion power, neutron wall loading, heat flux to divertor plate, structural restriction on major radius, device size, maximum toroidal magnetic field, poloidal field power supply and so on. Theoretical scaling law for the available maximum toroidal β value determined by ballooning mode instability is used. The toroidal magnetic field on plasma axis can be expressed by the aspect ratio A for a given maximum field at the toroidal field coil conductor. Empirical scaling law for the electron energy confinement and neoclassical heat conductivity for the ion are employed. These confinement times can be expressed by the plasma minor radius a and A through the maximum available β value and the toroidal field on axis. In the similar way, most of the physics and engineering requirements can be mapped on the a-A diagram. This diagram enables us to make systematic and wide range of parameter surveys of the device. In particular, this offers a clear perspective on the device parameters, which can mitigate the engineering difficulties and can also realize the required plasma performances.

Original languageEnglish
Pages (from-to)628-637
Number of pages10
JournalJournal of Nuclear Science and Technology
Volume19
Issue number8
DOIs
Publication statusPublished - 1982

Fingerprint

Experimental reactors
Fusion reactions
Requirements engineering
fusion
Scaling laws
reactors
Plasmas
Physics
Magnetic fields
Plasma confinement
engineering
Plasma stability
scaling laws
diagrams
Ignition
Heat flux
Aspect ratio
Thermal conductivity
Neutrons
ballooning modes

Keywords

  • alpha particle confinement
  • empirical energy confinement scaling
  • fusion power output
  • neutron wall loading
  • self-ignition condition
  • tokamak reactor
  • toroidal beta value

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Cite this

Sugihara, M., Fujisawa, N., Shimada, R., Ueda, K., Saito, S., & Hatayama, A. (1982). Plasma Design Considerations of Near Term Tokamak Fusion Experimental Reactor. Journal of Nuclear Science and Technology, 19(8), 628-637. https://doi.org/10.3327/jnst.19.628

Plasma Design Considerations of Near Term Tokamak Fusion Experimental Reactor. / Sugihara, Masayoshi; Fujisawa, Nobol; Shimada, Ryuichi; Ueda, Kojyu; Saito, Seiji; Hatayama, Akiyoshi.

In: Journal of Nuclear Science and Technology, Vol. 19, No. 8, 1982, p. 628-637.

Research output: Contribution to journalArticle

Sugihara, M, Fujisawa, N, Shimada, R, Ueda, K, Saito, S & Hatayama, A 1982, 'Plasma Design Considerations of Near Term Tokamak Fusion Experimental Reactor', Journal of Nuclear Science and Technology, vol. 19, no. 8, pp. 628-637. https://doi.org/10.3327/jnst.19.628
Sugihara, Masayoshi ; Fujisawa, Nobol ; Shimada, Ryuichi ; Ueda, Kojyu ; Saito, Seiji ; Hatayama, Akiyoshi. / Plasma Design Considerations of Near Term Tokamak Fusion Experimental Reactor. In: Journal of Nuclear Science and Technology. 1982 ; Vol. 19, No. 8. pp. 628-637.
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