Heat Flux Calculation and Problem of Flaking of Boron Carbide Coatings on the Faraday Screen of the ICRH Antennas During Tore Supra High Power, Long Pulse Operation

Journal Article · Sat Jan 01 00:00:00 EST 2011 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2011.03.120· OSTI ID:1120477

Corre, Y. ^[1]; Lipa, M. ^[2]; Agarici, G. ^[3]; Basiuk, V. ^[2]; Colas, L. ^[4]; Courtois, X. ^[5]; Dumont, R. J. ^[1]; Ekedahl, A. ^[6]; Gardarein, J. L. ^[7]; Klepper, C Christopher ^[8]; Martin, V. ^[6]; Moncada, V. ^[5]; Portafaix, C. ^[5]; Rigollet, F. ^[7]; Tawizgant, R. ^[5]; Travere, J. M. ^[5]; Valliez, K. ^[5]

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1. French Atomic Energy Commission (CEA), Cadarache, St. Paul lez Durance
2. CEA IRFM, St. Paul-lez-Durance, France
3. Fusion for Energy (F4E), Barcelona, Spain
4. French Atomic Energy Commission (CEA)
5. CEA, St. Paul Les Durance, France
6. French Atomic Energy Commission (CEA), Institute for Magnetic Fusion Research (IRFM)
7. University of Aix, Marseille, France
8. ORNL

Reliable and repetitive high power and long pulse tokamak operation is strongly dependant of the ability to secure the Plasma Facing Components (PFCs). In Tore Supra, a network of 7 infrared (IR) video cameras is routinely used to prevent PFCs overheating and damage in selected regions. Real time feedback control and offline analysis are essential for basic protection and understanding of abnormal thermal events. One important limitation detected by the IR real time feed-back loop during high power RF operation (injected power of 9.5 MW over 26 s and 12 MW over 10 s have been achieved respectively in 2006 and 2008) is due to the interaction between fast ions which increase the power flux density and flaking of the boron carbide coatings on the Faraday screen box of the ICRH antennas. An IR-based experimental procedure is proposed in order to detect new flakes during plasma operation. The thermal response of the B4C coating is studied with and without flaking during plasma operation. The experimental heat flux deposited by fast ion losses on the Faraday screen is calculated for high (3.8 T) and low magnetic field (2 T) during high RF power operation (with fundamental hydrogen minority and second harmonic ICRH heating schemes respectively). The paper addresses both thermal science issues applied to machine protection and limitation due to fast ions issues during high RF power, long pulse operation. Safety margin to critical heat flux and number of fatigue cycles under heat load are presented in the paper.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 1120477
• Journal Information: Fusion Engineering and Design, Vol. 86, Issue 4-5; ISSN 0920-3796
• Country of Publication: United States
• Language: English