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
Creators
- 1. CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France)
- 2. Fusion for Energy, C/Josep Pla 2, 08019 Barcelona (Spain)
- 3. IUSTI UMR-CNRS 65-95. Universite de Provence, Marseille (France)
- 4. USA ORNL, Fusion Energy Division, Oak Ridge, TN 37831-6169 (United States)
Description
Highlights: → We summarize the problem of flaking of the B4C coatings in the scope of PFC protection with infrared Real Time Control safety system, during high ICRH power, long discharge operation in the Tore Supra tokamak → We compute the heat flux deposited by fast ions on the Faraday screen of the ICRH antennas → The heat loads attributed to fast ions are evaluated during fundamental hydrogen minority (B = 3.7 T) and second harmonic (B = 2 T) ICRH heating scenarios → We investigate the safety margin to critical heat flux and number of fatigue cycles under heat load for the two heating scenarios. - Abstract: 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.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2011.03.120Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2011.03.120;
- PII
- S0920-3796(11)00395-4;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 86
- Journal Issue
- 4-5
- Journal Page Range
- p. 429-441
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43065224
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- ANTENNAS; BORON CARBIDES; COATINGS; CONTROL; CRITICAL HEAT FLUX; FATIGUE; FEEDBACK; FIRST WALL; HEATING LOAD; ICR HEATING; REAL TIME SYSTEMS; SAFETY; SAFETY MARGINS; TORE SUPRA TOKAMAK
- Descriptors DEC
- BORON COMPOUNDS; CARBIDES; CARBON COMPOUNDS; CLOSED PLASMA DEVICES; ELECTRICAL EQUIPMENT; EQUIPMENT; HEAT FLUX; HEATING; HIGH-FREQUENCY HEATING; MECHANICAL PROPERTIES; PLASMA HEATING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOKAMAK DEVICES
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.