E.R. Solano G. Birkenmeier C. Silva E. Delabie J.C. Hillesheim A. Baciero I. Balboa M. Baruzzo A. Boboc M. Brix C. Bourdelle I.S. Carvalho P. Carvalho C.D. Challis M. Chernyshova A. Chomiczewska R. Coelho T. Craciunescu E. de la Cal E. de la Luna R. Dumont P. Dumortier M. Fontana J.M. Fontdecaba L. Frassinetti D. Gallart J. Garcia C. Giroud W. Gromelski R.B. Henriques J. Hall A. Ho L. Horvath P. Jacquet I. Jepu E. Joffrin A. Kappatou P.J. Lomas D.L. Keeling D.B. King E. Kowalska-Strzęciwilk M. Lennholm E. Lerche E. Litherland-Smith V.G. Kiptily K.K. Kirov A. Loarte B. Lomanowski C.F. Maggi J. Mailloux M.J. Mantsinen M. Maslov A.G. Meigs I. Monakhov R.B. Morales A.H. Nielsen D. Nina C. Noble E. Pawelec M. Poradzinski G. Pucella P. Puglia D. Réfy J.J. Rasmussen E. Righi-Steele F.G. Rimini T. Robinson M. Sertoli S.A. Silburn P. Sirén Ž. Štancar H.J. Sun G. Szepesi D. Taylor B. Thomas E. Tholerus G. Verdoolaege P. Vincenzi B. Viola N. Vianello T. Wilson
Preprint Published
D.B. King R. Sharma C.D. Challis A. Bleasdal E.G. Delabie D. Douai D. Keeling E. Lerche M.Lennholm J. Mailloux G. Matthews M. Nicassio Z. Stancar T. Wilson
Neutral Beam Injection (NBI) is a flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and mixed DeuteriumTritium Experimental campaign (DTE2) on the JET device. High NBI power was required for high fusion yield and alpha particle studies and to …
Preprint PublishedA V Dudkovskaia J W Connor D Dickinson P Hill K Imada S Leigh H R Wilson
A nonlinear 4-dimensional drift island theory derived in (Imada et al 2019 Nucl. Fusion 59 046016 and references therein) provides qualitative predictions of the plasma response to a stationary neoclassical tearing mode (NTM) magnetic island in a low beta, large aspect ratio tokamak plasma. (Dudkovskaia et al 2021 Plasma Phys. Control. Fusion 63 05…
PublishedS.N.Gerasimov L.R.Baylor A.Boboc I.S.Carvalho P.Carvalho I.H.Coffey D.Craven J.Flanagan A.Huber V.Huber S.Jachmich I.Jepu E.Joffrin D.Kos S.I.Krasheninnikov U.Kruezi M.Lehnen P.J.Lomas A.Manzanares M.Maslov A.Peacock P.Puglia S.Silburn F.G.Rimini R.D.Smirnov D.Shiraki C.Stuart H.Sun J.Wilson L.E.Zakharov JET Contributors
In 2019, the JET-ILW was equipped with a Shattered Pellet Injector (SPI) system with a wide capability to allow studies on the efficacy of shattered pellets in reducing the electro-magnetic and the thermal loads during disruptions and the avoidance/suppression of the formation of runaway electrons. The fully commissioned system became operationa…
PreprintHendrik Meyer the STEP Plasma Control Heating & Current Drive Team
With steady progress on ITER project and the design of DEMO, the international community is now entering an era in which fusion power on the grid could become a reality within the next 20 – 30 years. In this environment the UK has started the ambitious Spherical Tokamak for Energy Production (STEP) programme, aiming to develop a compact protot…
PreprintT. Wilson S.J. Freethy M. Henderson A Köhn-Seeman I. Konoplev S. Saarelma D. Speirs R.G.L. Vann the STEP team
The UK’s Spherical Tokamak for Energy Production (STEP) reactor design program is now exclusively investigating concepts using microwave-based heating and current drive (HCD) systems. Electron Bernstein Wave (EBW) HCD is a relatively immature technology compared to Electron Cyclotron (EC) HCD but is of interest due to the promise of high current…
PreprintB.S. Patel D. Dickinson C.M. Roach H.R. Wilson
Spherical tokamaks (STs) have been shown to possess properties desirable for a fusion power plant such as achieving high plasma β and having increased vertical stability. To understand their confinement properties in a reactor relevant regime a 1GW fusion power spherical tokamak plasma equilibrium was analysed using linear gyrokinetics to deter…
Preprint PublishedD. B. King M. Nicassio A. Ash C. Balshaw A. Barth D. Ciric I. E. Day E. Delabie H. El-Haroun T. T. C. Jones D. Keeling R. King S. Marsden R. McAdams A. McShee S. Merriman A. Shepherd R. Sharma I. Turner T. Wilson
Neutral Beam Injection (NBI) is a very flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and Deuterium–Tritium Experimental campaign (DTE2) to be undertaken in the JET device. In particular, experiments for high fusion yield and alpha particl…
PreprintS.F. Smith S.J.P. Pamela A. Fil M. Hölzl G.T.A. Huijsmans A. Kirk D. Moulton O. Myatra A.J. Thornton H.R. Wilson
The high heat fluxes to the divertor during edge localised mode (ELM) instabilities have to be reduced for a sustainable future tokamak reactor. A solution to reduce the heat fluxes could be the Super-X divertor, this divertor configuration will be tested on MAST-U. ELM simulations for MAST-U Super-X tokamak plasmas have been obtained, using JOR…
PreprintM. R. Hardman F. I. Parra C. Chong T. Adkins M. S. Anastopoulos-Tzanis M. Barnes D. Dickinson J. F. Parisi H. Wilson
Ion-gyroradius-scale microinstabilities typically have a frequency comparable to the ion transit frequency. Hence, it is conventionally assumed that passing electrons respond adiabatically in ion-gyroradius-scale modes, due to the small electron-to-ion mass ratio and the large electron transit frequency. However, in gyrokinetic simulations of io…
Preprint Published