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Turbulence-reduced high-performance scenarios in Wendelstein 7-X

Authors :
O.P. Ford
M. Beurskens
S.A. Bozhenkov
S. Lazerson
L. Vanó
A. Alonso
J. Baldzuhn
C.D. Beidler
C. Biedermann
R. Burhenn
G. Fuchert
D. Hartmann
M. Hirsch
A. Langenberg
H. Laqua
P. McNeely
N. Pablant
E. Pasch
F. Reimold
T. Romba
N. Rust
R. Schroeder
E.R. Scott
T. Stange
H.M. Smith
D. Gradic
R.C. Wolf
D. Zhang
the W7-X Team
Source :
Nuclear Fusion, Vol 64, Iss 8, p 086067 (2024)
Publication Year :
2024
Publisher :
IOP Publishing, 2024.

Abstract

In the Wendelstein 7-X (W7-X) stellarator, turbulence is the dominant transport mechanism in most discharges. This leads to a ‘clamping’ of ion temperature over a wide range of heating power, predominantly flat density profiles where hollow profiles driven by neoclassical thermo-diffusion would be expected and by rapid impurity transport in injection experiments. Significantly reduced turbulent transport is observed in the presence of strong core density gradients found transiently after core pellet injection and irregularly after boronisation or boron pellet injection. Density peaking is also achieved in a controlled manner in purely neutral beam heated discharges where particle transport analysis reveals an abrupt reduction in the main-ion particle flux leading to significant density profile peaking not explained by the NBI particle source alone. The plasmas exhibit a heat diffusivity of around $\chi = 0.25 \pm 0.1\,\mathrm{m}^2\ \mathrm{s}^{-1}$ at mid radius, a factor of around 4 lower than ECRH dominated discharges. Despite the improved confinement, the achieved ion temperature is limited by broader heat deposition and the lower power-per-particle given the higher density. This is overcome with limited reintroduction of ECRH power, where the low heat diffusivity diffusivity is maintained, the density rise supressed and ion temperatures above the clamping limit are achieved. The applicability of these plasmas for a high performance scenario on transport relevant time scales is assessed, including initial predictions for planned heating upgrades of W7-X, based on a range of assumptions about particle transport.

Details

Language :
English
ISSN :
17414326 and 00295515
Volume :
64
Issue :
8
Database :
Directory of Open Access Journals
Journal :
Nuclear Fusion
Publication Type :
Academic Journal
Accession number :
edsdoj.196369daf9f3484485194277625dba32
Document Type :
article
Full Text :
https://doi.org/10.1088/1741-4326/ad5e99