Help Privacy Policy Disclaimer
  Advanced SearchBrowse




Journal Article

Overview of physics basis for ITER


Kardaun,  O.
Tokamak Theory (TOK), Max Planck Institute for Plasma Physics, Max Planck Society;


Sugihara,  M.
Experimental Plasma Physics 2 (E2), Max Planck Institute for Plasma Physics, Max Planck Society;

External Resource
No external resources are shared
Fulltext (public)
There are no public fulltexts stored in PuRe
Supplementary Material (public)
There is no public supplementary material available

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.

Cite as: http://hdl.handle.net/11858/00-001M-0000-0027-3C86-1
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.