Physics and technology in the ion-cyclotron range of frequency on Tore Supra and TITAN test facility: implication for ITER

Journal Article · Tue Jan 01 04:00:00 EST 2013 · Nuclear Fusion

DOI:https://doi.org/10.1088/0029-5515/53/8/083012· OSTI ID:1089339

Litaudon, X ^[1]; Bernard, J. M. ^[2]; Colas, L. ^[1]; Dumont, R. J. ^[3]; Argouarch, A. ^[3]; Bottollier-Curtet, H. ^[2]; Bremond, S. ^[2]; Champeaux, S. ^[2]; Corre, Y. ^[3]; Dumortier, P. ^[4]; Firdaouss, M. ^[2]; Guilhem, D. ^[2]; Gunn, J. P. ^[2]; Gouard, Ph. ^[5]; Hoang, G T ^[2]; Jacquot, Jonathan ^[2]; Klepper, C Christopher ^[6]; Kubic, M. ^[2]; Kyrytsya, V. ^[4]; Lombard, G. ^[2] ; Milanesio, D. ^[7]; Messiaen, A. ^[4]; Mollard, P. ^[2]; Meyer, O. ^[3]; Zarzoso, D. ^[2]

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1. CEA, France
2. CEA, IRFM, France
3. CEA Cadarache, St. Paul lex Durance, France
4. ERM-KMS, Association EURATOM-Belgian State, Brussels, Belgium
5. CEA, DAM, DIF, Arpajon cedex, France
6. ORNL
7. Politecnico di Torino

To support the design of an ITER ion-cyclotron range of frequency heating (ICRH) system and to mitigate risks of operation in ITER, CEA has initiated an ambitious Research & Development program accompanied by experiments on Tore Supra or test-bed facility together with a significant modelling effort. The paper summarizes the recent results in the following areas: Comprehensive characterization (experiments and modelling) of a new Faraday screen concept tested on the Tore Supra antenna. A new model is developed for calculating the ICRH sheath rectification at the antenna vicinity. The model is applied to calculate the local heat flux on Tore Supra and ITER ICRH antennas. Full-wave modelling of ITER ICRH heating and current drive scenarios with the EVE code. With 20 MW of power, a current of 400 kA could be driven on axis in the DT scenario. Comparison between DT and DT(3He) scenario is given for heating and current drive efficiencies. First operation of CW test-bed facility, TITAN, designed for ITER ICRH components testing and could host up to a quarter of an ITER antenna. R&D of high permittivity materials to improve load of test facilities to better simulate ITER plasma antenna loading conditions.

• Research Organization: Oak Ridge National Laboratory (ORNL)
• Sponsoring Organization: SC USDOE - Office of Science (SC)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1089339
• Journal Information: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 8 Vol. 53; ISSN 0029-5515
• Country of Publication: United States
• Language: English