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          Institute: MPI für Plasmaphysik     Collection: Articles, Books, Inbooks     Display Documents



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ID: 60420.0, MPI für Plasmaphysik / Articles, Books, Inbooks
Overview of physics basis for ITER
Authors:Mukhovatov, V.; Shimada, M.; Chudnovskiy, A. N.; Costley, A. E.; Gribov, Y.; Federici, G.; Kardaun, O.; Kukushkin, A. S.; Polevoi, A.; Pustovitov, V. D.; Shimomura, Y.; Sugie, T.; Sugihara, M.; Vayakis, G.
Language:English
Research Context:30th European Physical Society Conference on Controlled Fusion and Plasma Physics, St. Petersburg, 2003-07-07 to 2003-07-11
Date of Publication (YYYY-MM-DD):2003
Title of Journal:Plasma Physics and Controlled Fusion
Journal Abbrev.:Plasma Phys. Control. Fusion
Volume:45
Issue / Number:12A
Start Page:A235
End Page:A252
Title of Issue:Invited Papers from the 30th European Physical Society Conference on Controlled Fusion and Plasma Physics
Copyright:Copyright © Institute of Physics and IOP Publishing Limited 2003
Review Status:Peer-review
Audience:Experts Only
Abstract / Description: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.
External Publication Status:published
Document Type:Article
Communicated by:N. N.
Affiliations:MPI für Plasmaphysik/TOK
External Affiliations:International 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
Identifiers:DOI:10.1088/0741-3335/45/12A/016
URL:http://stacks.iop.org/0741-3335/45/A235
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