D. Brunetti C. J. Ham J. P. Graves E. Lazzaro S. Nowak A. Mariani C. Wahlberg W. A. Cooper E. R. Solano S. Saarelma L. Frassinetti M. Fontana A. Kleiner G. Bustos Ramirez E. Viezzer JET contributors
The analysis of quiescent discharges exhibiting edge harmonic magnetoydrodynamic activity in the JET-Carbon wall machine is presented. It is observed that the quiescent phase with multiple-n harmonic oscillations is sustained until a threshold in pedestal electron density and collisionality is crossed. The macroscopic pedestal parameters associated…
Preprint PublishedE. Flynn P. Cooper O. Crofts A. Loving Z. Vizvary A. Wilde
DEMO is a key part of the EU fusion roadmap, where the programme is reaching the end of the pre-conceptual phase with a gate review in 2020. As part of the work to complete this phase, eight Key Design Integration Issues (KDII’s) have been identified as critical to the programme. Within KDII#1 (wall protection limiters) the feasibility of the Inn…
Preprint PublishedZ. Vizvary W. Arter C. Bachmann T. R. Barrett B. Chuilon P. Cooper M. Firdaouss T. Franke J. Gerardin R. Gowland M. Kovari F. Maviglia L. M. Richiusa E. V. Rosa Adame C. Vorpahl A. Wilde Y. Xue
The anticipated heat flux limit of the European DEMO first wall is ~1MW/m2. During transient and off normal events, the heat load deposited on the wall would be much larger than that the steady state heat load and exceed the first wall limit, therefore the breeding blanket first wall needs to be protected in such events. This involves de…
Preprint PublishedD. Brunetti C. J. Ham J. P. Graves C. Wahlberg W. A. Cooper
Anisotropy and some limiting toroidal flow effects on the stability of non resonant ideal magnetohydrodynamic modes in hybrid shaped tokamak plasmas are investigated within the ideal MHD infernal mode framework. Such effects are found to alter the plasma magnetic well/hill, which can be interpreted as imparing the average curvature, and the stre…
Preprint PublishedZ. Vizvary D. Iglesias D. Cooper R. Crowe V. Riccardo
The blanket attachment has to cope with gravity, thermal and electromagnetic loads, also it has to be installed and serviced by remote handling. Pre-stressed components suffer from stress relaxation in irradiated environments such as DEMO. To circumvent this problem pre-stressed component should be either avoided or shielded, and where possible key…
Preprint PublishedI.T. Chapman M. Becoulet T. Bird J. Canik M. Cianciosa W.A. Cooper T. Evans N. Ferraro C. Fuchs M. Gryaznevich Y. Gribov C. Ham J. Hanson G. Huijsmans A. Kirk S. Lazerson Y. Liang I. Lupelli R.A. Moyer C. Nührenberg F. Orain D. Orlov,
The three dimensional plasma boundary displacements induced by applied nonaxisymmetric magnetic perturbations have been measured in ASDEX Upgrade, DIII-D, JET, MAST and NSTX. The displacements arising from applied resonant magnetic perturbations (RMPs) are measured up to ±5% of the minor radius in present day machines. Good agreement can be found …
PublishedA. D. Turnbull N. M. Ferraro V. A. Izzo E. A. Lazarus J.-K. Park W. A. Cooper S. P. Hirshman L. L. Lao M. J. Lanctot S. Lazerson Y. Q. Liu A. Reiman F. Turco
With the installation of non-axisymmetric coil systems on major tokamaks for the purpose of studying the prospects of ELM-free operation, understanding the plasma response to the applied fields is a crucial issue. Application of different response models, using standard tools, to DIII-D discharges with applied non-axisymmetric fields from internal …
PublishedI.T. Chapman W.A. Cooper A. Kirk C.J. Ham J.R. Harrison A. Patel S.D. Pinches R. Scannell A.J. Thornton The Mast Team
The distortion of the plasma boundary when three-dimensional resonant magnetic perturbations are applied has been measured in MAST H-mode plasmas. When the n = 3 resonant magnetic perturbations are applied to control edge localised modes, the plasma experiences a strong toroidal corrugation. The displacement of the plasma boundary is measured at va…
PublishedW A Cooper J P Graves O Sauter S P Hirshman I T Chapman M Gobbin L Marrelli P Martin I Predebon D Terranova
Magnetohydrodynamic equilibrium states with a three-dimensional helical core are computed to model the MAST spherical tokamak and the RFX-mod reversed field pinch. The boundary is fixed as axisymmetric. The MAST equilibrium state has the appearance of an internal kink mode and is obtained under conditions of weak reversed central shear. The RFX-mod…
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