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Prospects for stead...
Prospects for steady-state scenarios on JET
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Litaudon, X. (author)
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Bizarro, J. P. S. (author)
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Challis, C. D. (author)
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Crisanti, F. (author)
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De Vries, P. C. (author)
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Lomas, P. (author)
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Rimini, F. G. (author)
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Tala, T. J. J. (author)
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Akers, R. (author)
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Andrew, Y. (author)
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Arnoux, G. (author)
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Artaud, J. F. (author)
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Baranov, Yu F. (author)
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Beurskens, M. (author)
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Brix, M. (author)
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Cesario, R. (author)
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De La Luna, E. (author)
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Fundamenski, W. (author)
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Giroud, C. (author)
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Hawkes, N. C. (author)
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Huber, A. (author)
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Joffrin, E. (author)
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Pitts, R. A. (author)
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- Rachlew, Elisabeth (author)
- KTH,Atom- och molekylfysik
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Reyes-Cortes, S. D. A. (author)
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Sharapov, S. E. (author)
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Zastrow, K. D. (author)
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Zimmermann, O. (author)
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(creator_code:org_t)
- 2007-08-29
- 2007
- English.
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In: Nuclear Fusion. - : IOP Publishing. - 0029-5515 .- 1741-4326. ; 47:9, s. 1285-1292
- Related links:
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https://urn.kb.se/re...
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https://doi.org/10.1...
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Abstract
Subject headings
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- In the 2006 experimental campaign, progress has been made on JET to operate non-inductive scenarios at higher applied powers (31 MW) and density (n(1) similar to 4 x 10(19) m(-3)), with ITER-relevant safety factor (q(95) similar to 5) and plasma shaping, taking advantage of the new divertor capabilities. The extrapolation of the performance using transport modelling benchmarked on the experimental database indicates that the foreseen power upgrade (similar to 45 MW) will allow the development of non-inductive scenarios where the bootstrap current is maximized together with the fusion yield and not, as in present-day experiments, at its expense. The tools for the long-term JET programme are the new ITER-like ICRH antenna (similar to 15 MW), an upgrade of the NB power (35 MW/20s or 17.5 MW/40s), a new ITER-like first wall, a new pellet injector for edge localized mode control together with improved diagnostic and control capability. Operation with the new wall will set new constraints on non-inductive scenarios that are already addressed experimentally and in the modelling. The fusion performance and driven current that could be reached at high density and power have been estimated using either 0D or 1-1/2D validated transport models. In the high power case (45 MW), the calculations indicate the potential for the operational space of the non-inductive regime to be extended in terms of current (similar to 2.5 MA) and density (n(1) > 5 x 10(19) m(-3)), with high beta(N) (beta(N) > 3.0) and a fraction of the bootstrap current within 60-70% at high toroidal field (similar to 3.5 T).
Keyword
- internal transport barriers
- real-time control
- advanced tokamak
- diii-d
- profile control
- itb plasmas
- tore-supra
- operation
- physics
- iter
Publication and Content Type
- ref (subject category)
- art (subject category)
Find in a library
To the university's database
- By the author/editor
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Litaudon, X.
-
Bizarro, J. P. S ...
-
Challis, C. D.
-
Crisanti, F.
-
De Vries, P. C.
-
Lomas, P.
-
show more...
-
Rimini, F. G.
-
Tala, T. J. J.
-
Akers, R.
-
Andrew, Y.
-
Arnoux, G.
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Artaud, J. F.
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Baranov, Yu F.
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Beurskens, M.
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Brix, M.
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Cesario, R.
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De La Luna, E.
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Fundamenski, W.
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Giroud, C.
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Hawkes, N. C.
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Huber, A.
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Joffrin, E.
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Pitts, R. A.
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Rachlew, Elisabe ...
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Reyes-Cortes, S. ...
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Sharapov, S. E.
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Zastrow, K. D.
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Zimmermann, O.
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show less...
- Articles in the publication
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Nuclear Fusion
- By the university
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Royal Institute of Technology