Modelling of LHCD profile control for high performance DT experiments on JET

Journal Article · Mon Sep 20 00:00:00 EDT 1999 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.59732· OSTI ID:21210453

Tala, T J. J.; Heikkinen, J A; Karttunen, S J; Paettikangas, T J. H. ^[1]; Soeldner, F X; Parail, V V; Baranov, Yu F; Taroni, A ^[2]

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1. Association Euratom-Tekes, VTT Energy, P.O. Box 1604, FIN-02044 VTT (Finland)
2. JET Joint Undertaking, Abingdon, Oxon OX14 SEA (United Kingdom)

Transport calculations with relevant lower hybrid current drive control have been performed with the JETTO transport code. The heat transport model and various particle transport models reproducing the experimental JET data have been used in JETTO for predictive high performance modelling. Application of 3.5 MW LHCD power provides a slightly inverted or flat q-profile across 70% of the plasma radius whereas, without LHCD the q-profile is monotonic during the flat-top phase. The results predict a fusion power up to 30 MW for the high performance DT plasmas in the optimised shear scenario at B{sub t}=3.4 T and I{sub p}=3.9 MA. Large uncertainties, however, still persist in particular on the particle transport which strongly influences on the modelling calculations. The presence of not well understood MHD instabilities is also likely to reduce the performance. The most optimistic model, still consistent with experimental results, predicts a fusion gain approaching Q=1.

• OSTI ID: 21210453
• Journal Information: AIP Conference Proceedings, Vol. 485, Issue 1; Conference: 13. topical conference on radio frequency power in plasmas, Annapolis, MD (United States), 12-14 Apr 1999; Other Information: DOI: 10.1063/1.59732; (c) 1999 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
COMPUTERIZED SIMULATION
D-T OPERATION
ELECTRIC CURRENTS
ELECTRON TEMPERATURE
HEAT TRANSFER
ION TEMPERATURE
J CODES
JET TOKAMAK
LOWER HYBRID CURRENT DRIVE
MAGNETOHYDRODYNAMICS
PERFORMANCE
PLASMA
PLASMA CONFINEMENT
PLASMA DENSITY
PLASMA INSTABILITY
PLASMA SIMULATION
RF SYSTEMS
SHEAR