Effect of q-profile modification by LHCD on internal transport barriers in JET
Creators
- 1. Euratom/UKAEA Fusion Association, Culham Science Centre, Abingdon, Oxon (United Kingdom)
- 2. Max-Planck-Institut fuer Plasmaphysik, Euratom-Association IPP, Garching (Germany)
- 3. Associazione Euratom/ENEA sulla Fusione, Centro Ricerche Energia ENEA-Frascati, Frascati, Rome (Italy)
- 4. Association Euratom-CEA pour la Fusion, CEA Cadarache, Saint Paul-lez-Durance (France)
- 5. Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ (United States)
- 6. Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA (United States)
Description
Optimized shear (OS) experiments in JET can generate an internal transport barrier (ITB) during a high power heating phase early in the plasma discharge. A strong link is generally observed between the formation of the barrier and the location of an integer q magnetic surface within a low magnetic shear (s=r/q(dq/dr)) region of the plasma. However, if the q-profile for such experiments is modified by applying lower hybrid heating and current drive (LHCD) before the main heating pulse, to provide a region of reduced or negative magnetic shear in the plasma core, ITBs can be formed the location of which does not exhibit any apparent association with a particular internal magnetic surface. Initial results suggest that q-profile modification using an LHCD prelude can also be used to reduce the heating power level required for ITB generation. (author)
Availability note (English)
Available online at the Web site for the journal Plasma Physics and Controlled Fusion (ISSN 1361-6587) http://www.iop.org/Additional details
Identifiers
- URL
- http://www.iop.org/;
Publishing Information
- Journal Title
- Plasma Physics and Controlled Fusion
- Journal Volume
- 43
- Journal Issue
- 7
- Journal Page Range
- p. 861-879
- ISSN
- 0741-3335
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 32034574
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BOUNDARY LAYERS; JET TOKAMAK; LOWER HYBRID CURRENT DRIVE; LOWER HYBRID HEATING; MAGNETIC SURFACES; RADIATION TRANSPORT; SHEAR
- Descriptors DEC
- CLOSED PLASMA DEVICES; HEATING; HIGH-FREQUENCY HEATING; LAYERS; MAGNETIC FIELD CONFIGURATIONS; NON-INDUCTIVE CURRENT DRIVE; PLASMA HEATING; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Notes
- This paper is an extended version of a contribution to the 27th EPS Conference on Controlled Fusion and Plasma Physics, held at Budapest, Hungary, June 2000