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  Comparison of ITER performance predicted by semi-empirical and theory-based transport models

Mukhovatov, V., Shimomura, Y., Polevoi, A., Shimada, M., Sugihara, M., Bateman, G., et al. (2003). Comparison of ITER performance predicted by semi-empirical and theory-based transport models. Nuclear Fusion, 43, 942-948. doi:10.1088/0029-5515/43/9/318.

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Mukhovatov, V.1, Author
Shimomura, Y.1, Author
Polevoi, A.1, Author
Shimada, M.1, Author
Sugihara, M.2, Author              
Bateman, G.1, Author
Cordey, J. G.1, Author
Kardaun, O.3, Author              
Pereverzev, G.3, Author              
Voitsekhovich, I.1, Author
Weiland, J.1, Author
Zolotukhin, O.1, Author
Chudnovskiy, A.1, Author
Kritz, A. H.1, Author
Kukushkin, A.4, Author              
Onjun, T.1, Author
Pankin, A.1, Author
Perkins, F. W.1, Author
Affiliations:
1ITER International Team, ITER Naka Joint Work Site, Naka-machi, Naka-gun, Ibaraki-ken 311-0193, Japan; Lehigh University, Bethlehem, PA 18015, USA; EURATOM-UKAEA Fusion Association, Culham Science Centre, Abingdon, UK; Equipe Turbulence Plasma, University of Provence, Marseilles, France; Chalmers University of Technology and EURATOM-NFR Association, Göteborg, Sweden; ITER International Team, ITER Garching Joint Work Site, Garching, Germany; Nuclear Fusion Institute, Russian Research Center 'Kurchatov Institute', Moscow, Russia; General Atomics 13-312, PO Box 85608, San Diego, CA 92186, USA, ou_persistent22              
2Experimental Plasma Physics 2 (E2), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856292              
3Tokamak Theory (TOK), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856309              
4Material Research (MF), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856328              

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 Abstract: The values of Q = (fusion power)/(auxiliary heating power) predicted for ITER by three different methods are compared. The first method utilizes an empirical confinement-time scaling and prescribed radial profiles of transport coefficients; the second approach extrapolates from specially designed ITER similarity experiments, and the third approach is based on partly theory-based transport models. The energy confinement time given by the ITERH-98(y, 2) scaling for an inductive scenario with a plasma current of 15 MA and a plasma density 15% below the Greenwald density is 3.7 s with one estimated technical standard deviation of ±14%. This translates, in the first approach, for levels of helium removal, and impurity concentration, that, albeit rather stringent, are expected to be attainable, into an interval for Q of [6–15] at the auxiliary heating power, Paux = 40 MW, and [6–30] at the minimum heating power satisfying a good confinement ELMy H-mode. All theoretical transport-model calculations have been performed for the plasma core only, whereas the pedestal temperatures were taken as estimated from empirical scalings. Predictions of similarity experiments from JET and of theory-based transport models that we have considered—Weiland, MMM, and IFS/PPPL—overlap with the prediction using the empirical confinement-time scaling within its estimated margin of uncertainty.

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Language(s): eng - English
 Dates: 2003
 Publication Status: Published in print
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 Rev. Type: Peer
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Title: Nuclear Fusion
  Alternative Title : Nucl. Fusion
Source Genre: Journal
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Publ. Info: Copyright © Institute of Physics and IOP Publishing Limited 2003
Pages: - Volume / Issue: 43 Sequence Number: - Start / End Page: 942 - 948 Identifier: -