ECRH-assisted plasma start-up with toroidally inclined launch: multi-machine comparison and perspectives for ITER
Creators
- Stober, J.1
- Hobirk, J.1
- Lunt, T.1
- Jackson, G.L.2
- Hyatt, A.W.2
- Luce, T.2
- Ascasibar, E.3
- Cappa, A.3
- Bae, Y.-S.4
- Joung, M.4
- Bucalossi, J.5
- Casper, T.6
- Gribov, Y.6
- Cho, M.-H.7
- Jeong, J.-H.7
- Namkung, W.7
- Park, S.-I.7
- Granucci, G.8
- Hanada, K.9
- Ide, S.10
- and others
- ASDEX Upgrade Team
- TJ-II Team
- ITPA 'Integrated Operations Scenarios' Group Members and Experts
- 1. Max-Planck-Institut fuer Plasmaphysik, EURATOM-Association, Garching (Germany)
- 2. General Atomics, PO Box 85608, San Diego, CA 92186-5608 (United States)
- 3. Laboratorio Nacional de Fusion, Asociacion EURATOM/CIEMAT, 28040, Madrid (Spain)
- 4. National Fusion Research Institute, Gwahangno 113, Yuseong-gu, Daejeon 305-333 (Korea, Republic of)
- 5. Association Euratom-CEA, Cadarache, F-13108 St Paul-lez-Durance (France)
- 6. ITER Organisation, Route de Vinon sur Verdon, F-13115 St Paul-lez-Durance (France)
- 7. Pohang University of Science and Technology, San 31, Hyoja-dong, Nam-gu, Pohang 790-784 (Korea, Republic of)
- 8. Associazione Euratom-ENEA sulla Fusione, IFP-CNR, Via R. Cozzi 53, 20125 Milano (Italy)
- 9. RIAM, Kyushu University, RIAM, Kasuga, Fukuoka 816-8580 (Japan)
- 10. Japan Atomic Energy Agency, 801-1, Mukouyama, Naka, Ibaraki-ken 311-0193 (Japan)
Description
Electron cyclotron resonance heating (ECRH)-assisted plasma breakdown is foreseen with full and half magnetic field in ITER. As reported earlier, the corresponding O1- and X2-schemes have been successfully used to assist pre-ionization and breakdown in present-day devices. This contribution reports on common experiments studying the effect of toroidal inclination of the ECR beam, which is ≥200 in ITER. All devices could demonstrate successful breakdown assistance for this case also, although in some experiments the necessary power was almost a factor of 2 higher compared with perpendicular launch. Differences between the devices with regard to the required power and vertical field are discussed and analysed. In contrast to most of these experiments, ITER will build up loop voltage prior to the formation of the field null due to the strong shielding by the vessel. Possible consequences of this difference are discussed.
Availability note (English)
Available from http://dx.doi.org/10.1088/0029-5515/51/8/083031Additional details
Identifiers
- DOI
- 10.1088/0029-5515/51/8/083031;
- PII
- S0029-5515(11)85659-0;
Publishing Information
- Journal Title
- Nuclear Fusion
- Journal Volume
- 51
- Journal Issue
- 8
- Journal Page Range
- [9 p.]
- ISSN
- 0029-5515
- CODEN
- NUFUAU
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43006293
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BREAKDOWN; ECR HEATING; ITER TOKAMAK; MAGNETIC FIELDS; PLASMA; START-UP
- Descriptors DEC
- CLOSED PLASMA DEVICES; HEATING; HIGH-FREQUENCY HEATING; PLASMA HEATING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS