Siobhan Smith Stanislas Pamela Howard Wilson Guido Huijsmans
Edge localised modes (ELMs) are magneto-hydrodynamic (MHD) instabilities that drive filamentary plasma eruptions in high confinement tokamak discharges [1]. Gaining an improved understanding of ELMs is important [2]; in future fusion reactors such as ITER, ELM heat fluxes will need to be limited to ensure durability of divertor materials [3]. A …
Preprint PublishedJ.E. Menard R. Majeski M. Ono N.N. Bakharev V.K. Gusev M. Gryaznevich D. Kingham S. McNamara P. Thomas K. Hanada J. Harrison B. Lloyd Y.S. Hwang B. Lipschultz H. Wilson Y. Nagayama Y. Ono Y. Takase M. Reinke K. Tobita Z. Gao F. Alladio R.J. Fonck
The spherical torus/tokamak (ST) is a potentially attractive configuration for narrowing scientific and technical gaps to a fusion demonstration power plant and as a more compact and/or modular fusion power source. Due to a reduced plasma surface area to volume ratio, the ST configuration offers the potential to access high power exhaust heat fl…
PreprintM.S. Anastopoulos-Tzanis B.D. Dudson C.J. Ham C.C. Hegna P.B. Snyder H.R. Wilson
A linear perturbation theory is used to model the MHD stability of tokamak equilibria under the application of external 3D magnetic perturbations [C.C. Hegna, Physics of Plasmas 21 :072502, 2014]. The symmetry breaking produces the coupling of toroidal n modes. We use ELITE [H.R. Wilson et al., Physics of Plasmas 9 :1277, 2002] to produ…
Preprint PublishedB. Patel C. Challis D. Dickinson L. Garzotti F. Koechl C. Roach G. Staebler H. Wilson
Spherical Tokamaks (STs) could provide a route towards a compact fusion reactor due to advantageous properties such as high plasma beta. A GW-scale ST plasma is explored where Q=10 and R=2.5m. In this design 110 MW of NBI is needed to provide 9 MA of noninductive current, where the remaining 12 MA is pressure driven. To penetrate into the core a 1 …
Preprint PublishedS.F. Smith S.J.P. Pamela A. Fil M. Hoelzl G.T.A. Huijsmans A. Kirk D. Moulton O. Myatra A.J. Thornton H.R. Wilson
ELM simulations for the MAST-U Super-X tokamak have been obtained, using the JOREK code. The JOREK visco-resistive MHD model has been used to obtain comparisons of divertor configurations. The simulations show a factor 10 decrease in the peak heat flux to the outer target of the Super-X in comparison to a conventional divertor configuration. A roll…
Preprint Published