Showing 1 - 10 of 14 Journals Results
2019
UKAEA-CCFE-PR(19)55
A. Fil D. Moulton B. Dudson B. Lipschultz K. Verhaegh O. Février O. Myatra C. Theiler M. Wensing EUROfusion MST1 teams the TCV team
In ITER and DEMO, achieving detachment at lower densities would allow to reduce the amount of impurity seeded and to improve confinement by running at lower separatrix densities. Analytic models predict that a increase of total flux expansion would allow such a reduction in upstream density at detachment. However, both experiments and modelling …
Preprint Published2018
UKAEA-CCFE-PR(18)82
James Harrison C. Theiler B. Lipschultz A. Perek R. Maurizio B. Linehan W. A. J. Vijvers B. P. Duval B. Labit U. Sheikh K. Verhaegh S. Henderson A. Karpushov O. Fevrier H. de Oliviera H. Reimerdes A. Merle X. Feng the TCV team and the EUROfusion MST1 team
Recent experiments on TCV have made significant progress toward partial detachment of the outer divertor in neutral beam heated H-mode plasmas. The heating power required to enter H-mode was measured in a range of divertor configurations, finding that, in the vicinity of the PL-H/ne curve, the threshold power is largely independent of the poloidal…
Preprint Published2018
UKAEA-CCFE-PR(18)69
M. Willensdorfer T.B. Cote M. Griener D.A. Ryan E. Strumberger W. Suttrop N. Wang M. Cavedon S.S. Denk M. Dunne R. Fischer J. Galdon-Quiroga C.J. Ham C.C. Hegna M. Hoelzl A. Kirk M. Maraschek F. Mink N. Leuthold F. Orain E. P. Seliunin H. Zohm the ASDEX Upgrade Team and the MST1 Team
The impact of the three-dimensional (3D) tokamak geometry from external magnetic perturbations (MPs) on the local edge stability has been examined in high confinement mode (H-mode) plasmas with edge localised modes (ELMs) in ASDEX Upgrade. The 3D geometry has been probed using rigidly rotating MP fields. The measured distortions of the plasma bound…
Preprint Published2018
UKAEA-CCFE-PR(18)54
O. Linder J. Citrin G.M.D. Hogeweij C. Angioni C. Bourdelle F.J. Casson E. Fable A. Ho F. Koechl M. Sertoli the EUROfusion MST1 Team the ASDEX Upgrade Team
Neoclassical and turbulent heavy impurity transport in tokamak core plasmas are determined by main ion temperature, density and toroidal rotation profiles. Thus, in order to reproduce experimental behaviour of W accumulation, integrated modelling of main ion heat and particle transport is a vital prerequisite. For the first time, the quasilinear …
Preprint Published2018
UKAEA-CCFE-PR(18)52
Michael Komm Stuart Henderson Sarah Elmore COMPASS team EUROfusion MST1 team
Partial detachment is the desired regime for the baseline burning plasma scenario in ITER and next-step devices, as it allows to disspate the majority of the energy carried by charged particles through the scrape-off-layer (SOL) and thus avoids localised heat flux deposition in the divertor region. The COMPASS tokamak is equipped with an open diver…
Preprint Published2018
UKAEA-CCFE-PR(18)34
N. R. Walkden B. Labit H. Reimerdes J. Harrison T. Farley P. Innocente F. Militello the TCV Team the MST1 Team
Tangentially viewing fast camera footage of the low-field side snowflake minus divertor in TCV is analysed across a four point scan in which the proximity of the two X-points is varied systematically. The apparent flow observed in the post-processed movie shows two distinct regions of the camera frame exhibiting differing flow patterns. One flow in…
Preprint Published2018
UKAEA-CCFE-PR(18)23
M. Carr A. Meakins M. Bernert P. David C. Giroud J. Harrison S. Henderson B. Lipschultz F. Reimold the EUROfusion MST1 Team ASDEX Upgrade team
Ray-tracing techniques are applied to bolometry, a diagnostic particularly sensitive to machine geometry due to the effect of volume sampling. Sightlines from the ASDEX-Upgrade bolometer foils were ray-traced with a path tracing algorithm, where the optical path is represented by a statistical bundle of ray paths connecting the foil surface with th…
Preprint Published2017
CCFE-PR(17)70
D. A. Ryan Y. Q. Liu A. Kirk W. Suttrop B. Dudson M. Dunne M. Willensdorfer the ASDEX-Upgrade team and the EUROfusion MST1 team
It has been previously demonstrated in (Li et al 2016 Nuclear Fusion 56 126007) that the optimum upper/lower coil phase shift ΔΦopt for alignment of RMP coils for ELM mitigation depends sensitively on q95, and other equilibrium plasma parameters. Therefore, ΔΦopt is expected to vary widely during the current ramp …
Preprint Published2017
L. Yueqiang A. Kirk L. Li Y. In R. Nazikian Y. Sun W. Suttrop B. Lyons D. Ryan S. Wang X. Yang L. Zhou EUROfusion MST1 team
Extensive modelling efforts of the plasma response to the resonant magnetic perturbation fields, utilized for controlling the edge localized mode (ELM), help to identify the edge-peeling response as a key factor, which correlates to the observed ELM mitigation in several tokamak devices, including MAST, ASDEX Upgrade, EAST, and HL-2A. The recently …
Published2016
CCFE-PR(17)18
A. Kirk A.J. Thornton J.R. Harrison F. Militello N.R. Walkden The MAST Team The EUROfusion MST1 Team
Clear filamentary structures are observed at the edge of tokamak plasmas. These filaments are ejected out radially and carry plasma in the far Scrape Off Layer (SOL) region, where they are responsible for producing most of the transport. A study has been performed of the characteristics of the filaments observed in L-mode plasma on MAST, using visi…
Preprint Published- 1
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