Predictions of fast wave heating, current drive, and current drive antenna arrays for advanced tokamaks

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The objective of the advanced tokamak program is to optimize plasma performance leading to a compact tokamak reactor through active, steady state control of the current profile using non-inductive current drive and profile control. To achieve these objectives requires compatibility and flexibility in the use of available heating and current drive systems--ion cyclotron radio frequency (ICRF), neutral beams, and lower hybrid. For any advanced tokamak, the following are important challenges to effective use of fast waves in various roles of direct electron heating, minority ion heating, and current drive: (1) to employ the heating and current drive systems to give ... continued below

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8 p.

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Batchelor, D.B.; Baity, F.W. & Carter, M.D. December 31, 1994.

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The objective of the advanced tokamak program is to optimize plasma performance leading to a compact tokamak reactor through active, steady state control of the current profile using non-inductive current drive and profile control. To achieve these objectives requires compatibility and flexibility in the use of available heating and current drive systems--ion cyclotron radio frequency (ICRF), neutral beams, and lower hybrid. For any advanced tokamak, the following are important challenges to effective use of fast waves in various roles of direct electron heating, minority ion heating, and current drive: (1) to employ the heating and current drive systems to give self-consistent pressure and current profiles leading to the desired advanced tokamak operating modes; (2) to minimize absorption of the fast waves by parasitic resonances, which limit current drive; (3) to optimize and control the spectrum of fast waves launched by the antenna array for the required mix of simultaneous heating and current drive. The authors have addressed these issues using theoretical and computational tools developed at a number of institutions by benchmarking the computations against available experimental data and applying them to the specific case of TPX.

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8 p.

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INIS; OSTI as DE96005434

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  • 15. international conference on plasma physics and controlled nuclear fusion research, Madrid (Spain), 26 Sep - 1 Oct 1994

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  • Other: DE96005434
  • Report No.: CONF-940933--48
  • Grant Number: AC05-84OR21400
  • Office of Scientific & Technical Information Report Number: 201786
  • Archival Resource Key: ark:/67531/metadc665071

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  • December 31, 1994

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  • June 29, 2015, 9:42 p.m.

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  • Jan. 25, 2016, 2:15 p.m.

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Batchelor, D.B.; Baity, F.W. & Carter, M.D. Predictions of fast wave heating, current drive, and current drive antenna arrays for advanced tokamaks, article, December 31, 1994; Tennessee. (digital.library.unt.edu/ark:/67531/metadc665071/: accessed November 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.