Heating and current drive systems for TPX

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Description

The heating and current drive (H and CD) system proposed for the TPX tokamak will consist of ion cyclotron, neutral beam, and lower hybrid systems. It will have 17.5 MW of installed H and CD power initially, and can be upgraded to 45 MW. It will be used to explore advanced confinement and fully current-driven plasma regimes with pulse lengths of up to 1,000 s.

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5 p.

Creation Information

Swain, D.; Goranson, P.; Halle, A. von; Bernabei, S. & Greenough, N. May 24, 1994.

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Description

The heating and current drive (H and CD) system proposed for the TPX tokamak will consist of ion cyclotron, neutral beam, and lower hybrid systems. It will have 17.5 MW of installed H and CD power initially, and can be upgraded to 45 MW. It will be used to explore advanced confinement and fully current-driven plasma regimes with pulse lengths of up to 1,000 s.

Physical Description

5 p.

Notes

INIS; OSTI as DE96004926

Source

  • 11. topical meeting on the technology of fusion energy, New Orleans, LA (United States), 19-24 Jun 1994

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  • Other: DE96004926
  • Report No.: CONF-940630--58
  • Grant Number: AC05-84OR21400
  • Office of Scientific & Technical Information Report Number: 188631
  • Archival Resource Key: ark:/67531/metadc666073

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  • May 24, 1994

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • Jan. 19, 2016, 2:20 p.m.

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Swain, D.; Goranson, P.; Halle, A. von; Bernabei, S. & Greenough, N. Heating and current drive systems for TPX, article, May 24, 1994; Tennessee. (digital.library.unt.edu/ark:/67531/metadc666073/: accessed September 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.