ITER startup studies in the DIII-D tokamak

被引：44

作者：

Jackson, G. L. ^{[1
]}

Casper, T. A. ^{[2
]}

Luce, T. C. ^{[1
]}

Humphreys, D. A. ^{[1
]}

Ferron, J. R. ^{[1
]}

Hyatt, A. W. ^{[1
]}

Lazarus, E. A. ^{[3
]}

Moyer, R. A. ^{[4
]}

Petrie, T. W. ^{[1
]}

Rudakov, D. L. ^{[4
]}

West, W. P. ^{[1
]}

机构：

[1] Gen Atom Co, San Diego, CA 92186 USA

[2] Lawrence Livermore Natl Lab, Livermore, CA 94551 USA

[3] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA

[4] Univ Calif San Diego, La Jolla, CA 92093 USA

来源：

NUCLEAR FUSION | 2008年 / 48卷 / 12期

关键词：

D O I：

10.1088/0029-5515/48/12/125002

中图分类号：

O35 [流体力学]; O53 [等离子体物理学];

学科分类号：

070204 ; 080103 ; 080704 ;

摘要：

A plasma initiation and current ramp up scenario envisioned for ITER has been simulated in DIII-D experiments. These discharges were limited on the low field side (LFS) during the initial current ramp up, as specified for the ITER baseline startup scenario. Initial experiments produced internal inductance (l(i)),higher than the design value for the ITER shaping coils, often leading to vertical instabilities. A modified startup with larger volume was developed to reduce l(i) in the current ramp up. This large-bore scenario, also limiting on the LFS, produced a lower l(i) and avoided the vertical instabilities. Feedback control of l(i), using the ohmic field coil power supply as the actuator, was successfully demonstrated. Such control may be useful in avoiding vertical instabilities and in providing access to sawtooth-free steady state and hybrid scenarios in ITER. Experiments at reduced inductive voltage and with electron cyclotron assist for breakdown and burnthrough have also been carried out. The Corsica equilibrium and transport code has modelled these data to provide validation of transport models used to simulate this phase of ITER discharges in order to yield more accurate extrapolation to ITER scenarios.

引用

页数：8

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