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  Overview of physics basis for ITER

Mukhovatov, V., Shimada, M., Chudnovskiy, A. N., Costley, A. E., Gribov, Y., Federici, G., et al. (2003). Overview of physics basis for ITER. Invited Papers from the 30th European Physical Society Conference on Controlled Fusion and Plasma Physics, A235-A252. doi:10.1088/0741-3335/45/12A/016.

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 Creators:
Mukhovatov, V.1, Author
Shimada, M.1, Author
Chudnovskiy, A. N.1, Author
Costley, A. E.1, Author
Gribov, Y.1, Author
Federici, G.1, Author
Kardaun, O.2, Author           
Kukushkin, A. S.1, Author
Polevoi, A.1, Author
Pustovitov, V. D.1, Author
Shimomura, Y.1, Author
Sugie, T.1, Author
Sugihara, M.3, Author           
Vayakis, G.1, Author
Affiliations:
1International Team, ITER Naka Joint Work Site, Naka-machi, Ibaraki-ken 311-0193, Japan; Nuclear Fusion Institute, RRC Kurchatov Institute, Moscow, Russia; International Team, ITER Garching Joint Work Site, Garching, Germany, ou_persistent22              
2Tokamak Theory (TOK), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856309              
3Experimental Plasma Physics 2 (E2), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856292              

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Free keywords: 30th European Physical Society Conference on Controlled Fusion and Plasma Physics, St. Petersburg, 2003-07-07 to 2003-07-11
 Abstract: ITER will be the first magnetic confinement device with burning DT plasma and fusion power of about 0.5 GW. Parameters of ITER plasma have been predicted using methodologies summarized in the ITER Physics Basis (1999 Nucl. Fusion 39 2175). During the past few years, new results have been obtained that substantiate confidence in achieving Q ≥ 10 in ITER with inductive H-mode operation. These include achievement of a good H-mode confinement near the Greenwald density at high triangularity of the plasma cross section; improvements in theory-based confinement projections for the core plasma, even though further studies are needed for understanding the transport near the plasma edge; improvement in helium ash removal due to the elastic collisions of He atoms with D/T ions in the divertor predicted by modelling; demonstration of feedback control of neoclassical tearing modes and resultant improvement in the achievable β-values; better understanding of edge localized mode (ELM) physics and development of ELM mitigation techniques; and demonstration of mitigation of plasma disruptions. ITER will have a flexibility to operate also in steady-state and intermediate (hybrid) regimes. The 'advanced tokamak' regimes with weak or negative central magnetic shear and internal transport barriers are considered as potential scenarios for steady-state operation. The paper concentrates on inductively driven plasma performance and discusses requirements for steady-state operation in ITER.

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Language(s): eng - English
 Dates: 2003
 Publication Status: Published in print
 Pages: -
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 Table of Contents: -
 Rev. Type: Peer
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Title: Invited Papers from the 30th European Physical Society Conference on Controlled Fusion and Plasma Physics
Source Genre: Issue
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Publ. Info: -
Pages: - Volume / Issue: - Sequence Number: - Start / End Page: A235 - A252 Identifier: -

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Title: Plasma Physics and Controlled Fusion
  Alternative Title : Plasma Phys. Control. Fusion
Source Genre: Journal
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Publ. Info: Copyright © Institute of Physics and IOP Publishing Limited 2003
Pages: - Volume / Issue: 45 (12A) Sequence Number: - Start / End Page: - Identifier: -