Improved confinement in JET hybrid discharges
2012 (English)In: Plasma Physics and Controlled Fusion, ISSN 0741-3335, E-ISSN 1361-6587, Vol. 54, no 9, 095001- p.Article in journal (Refereed) Published
A new technique has been developed to produce plasmas with improved confinement relative to the H 98,y2 scaling law (ITER Physics Expert Groups on Confinement and Transport and Confinement Modelling and Database ITER Physics Basics Editors and ITER EDA 1999 Nucl. Fusion 39 2175) on the JET tokamak. In the mid-size tokamaks ASDEX upgrade and DIII-D heating during the current formation is used to produce a flat q-profile with a minimum close to 1. On JET this technique leads to q-profiles with similar minimum q but opposite to the other tokamaks not to an improved confinement state. By changing the method utilizing a faster current ramp with temporary higher current than in the flattop (current overshoot) plasmas with improved confinement (H 98,y2=1.35) and good stability (Î² N3) have been produced and extended to many confinement times only limited by technical constraints. The increase in H 98,y2-factor is stronger with more heating power as can be seen in a power scan. The q-profile development during the high power phase in JET is reproduced by current diffusion calculated by TRANSP and CRONOS. Therefore the modifications produced by the current overshoot disappear quickly from the edge but the confinement improvement lasts longer, in some cases up to the end of the heating phase.
Place, publisher, year, edition, pages
2012. Vol. 54, no 9, 095001- p.
ASDEX upgrade, Current overshoot, Good stability, Heating phase, Heating power, High-power, Hybrid discharges, JET tokamak, Q profiles, Technical constraints, Electric discharges, Magnetoplasma, Plasma stability, Tokamak devices
IdentifiersURN: urn:nbn:se:kth:diva-101336DOI: 10.1088/0741-3335/54/9/095001ISI: 000308046300008ScopusID: 2-s2.0-84864484312OAI: oai:DiVA.org:kth-101336DiVA: diva2:548216
QC 201208302012-08-302012-08-272012-10-25Bibliographically approved