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Improved confinement in JET hybrid discharges

Author
Abstract

A new technique has been developed to produce plasmas with improved confinement relative to the H-98,H-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,H-y2 = 1.35) and good stability (beta(N) approximate to 3) have been produced and extended to many confinement times only limited by technical constraints. The increase in H-98,H-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.

Year of Publication
2012
Journal
Plasma Physics and Controlled Fusion
Volume
54
Issue
9
Number of Pages
095001
Date Published
Sep
Type of Article
Article
ISBN Number
0741-3335
URL
http://www.iop.org/Jet/article?EFDP10061&EFDP10065
DOI
10.1088/0741-3335/54/9/095001
PId
c6de3db62ee755182e9963d63cb93ce8
Alternate Journal
Plasma Phys. Control. Fusion
Label
OA
Journal Article
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