E. Nasr S. Wimbush P Noonan P. Harris R. Gowland & A. Petrov
Spherical Tokamak for Energy Production (STEP) requires high-field magnet designs and has therefore adopted REBCO-based high temperature superconductor (HTS). HTS enables the Toroidal Field (TF) coils to be re-mountable, which unlocks STEP’s vertical maintenance approach, however, re-mountable joints, approximately 18 GJ of stored energy, and lim…
PreprintH Meyer the STEP Team
The programme to design plasma scenarios for the Spherical Tokamak for Energy Production (STEP), a reactor concept aiming at net electricity production, seeks to exploit the inherent advantages of the spherical tokamak (ST) while making conservative assumptions about plasma performance. This approach is motivated by the large gap between present-da…
PreprintP Methven
This paper sets the context for those that follow in this Special Edition by describing why STEP (Spherical Tokamak for Energy Production) has been launched, what it aims to achieve (benefits) and, principally, how the whole programme will be delivered (strategy). The paper draws on work on major project delivery and organisation design and ap…
PreprintA. Fil L. Henden S. Newton T. Hender M. Hoppe
Generation of Runaway Electrons during plasma disruptions, and their potential impact on the plasma facing components, is of great concern for ITER and future reactors based on the tokamak concept. The STEP (Spherical Tokamak for Energy Production) programme aims at producing net energy from a prototype fusion energy plant. At its current design po…
PreprintX. Litaudon U. Fantz R. Villari V. Toigo M.- H. Aumeunier J.- L. Autran P. Batistoni E. Belonohy S. Bradnam M. Cecchetto A. Colangeli F. Dacquait M. Dentan M. De Pietri J. Eriksson M. Fabbri G. Falchetto L. Figini J. Figueiredo D. Flammini N. Fonnesu L. Frassinetti R. Garcia-Alia M. Garcia-Munoz Z. Ghani J. Gonzalez-Martin E. Grelier L. Di Grazia B. Grove C. L. Grove A. Gusarov A. Hjalmarsson O. Hyvärinen V. Ioannou-Sougleridis L. Jones H.- T. Kim M. Kłosowski M. Kocan B. Kos L. Kos D. Kotnik E. Laszynska D. Leichtle I. Lengar E. Leon A. J. Lopez-Revelles S. Loreti M. Loughlin K.G. Mcclements G. Mariano M. Mattei K. Mergia J. Mietelski R. Mitteau S. Moindjie D. Munteanu R. Naish C. Nobs L. W. Packer S. Pamela R. Pampin A. Pau A. Peacock E. Peluso Y. Peneliau J. Peric V. Radulović F. Rimini D. Ricci L. Sanchis Sanchez P. Sauvan M.I. Savva A. Snicker L. Snoj I. E. Stamatelatos Ž. Štancar N. Terranova T. Vasilopoulou R. Vila J. Waterhouse A. Žohar The Nbtf Team The Jet Contributors The Eurofusion Tokamak Exploitation Team
ITER is of key importance in the European fusion roadmap as it aims to prove the scientific and technological feasibility of fusion as a future energy source. The EUROfusion consortium of labs is contributing to the preparation of ITER scientific exploitation and operation and aspires to exploit ITER outcomes in view of DEMO. The paper provides …
PreprintS. Chen N. Correa Villanueva S. Kirk S. Capp O. Fordham A. Reeves S. Jones R. Khan A. Sergi C. Thompson
During development of the UKAEA’S Spherical Tokamak for Energy Production (STEP), assessment of manufacturing strategies for the inboard shield identified several gaps in knowledge. Limits arose from the modularization of this component, geometric constraints of tungsten ceramic forming, joining with low-activation interlayers and dissimilar j…
PreprintV.G. Kiptily P.J. Bonofiglo T. Craciunescu J. Eriksson M. Fitzgerald V. Goloborodko M. Nocente S. Menmuir M. Podestà M. Poradzinski D. Rigamonti Z. Stancar S.E. Sharapov H. Sun D.M. Taylor M. Tardocchi P. Beaumont F. Belli F.E. Cecil C.D. Challis R. Coelho M. Curuia R. Dumont J. Garcia M. Garcia-Munoz Z. Ghani Ye. Kazakov D. Keeling E. Lerche C.F. Maggi J. Mailloux P. Mantica M.J. Mantsinen D. Marocco C. Perez von Thun F. Rimini
The fusion reaction between deuterium and tritium, D(T,n)4He is the main source of energy in future thermonuclear reactors. Charged fusion products of this reaction, α-particles (4He-ions), are born with an average energy of 3.5 MeV. Transferring energy to the thermal plasma during their slowing down, the…
PreprintD.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 PublishedR. T. Osawa S. L. Newton D. Moulton S. S. Henderson V. Badicel A. Hudoba
In order to achieve a compatible solution between the divertors and the core, SOLPS-ITER simulations were performed on STEP (Spherical Tokamak for Energy Production) connected double-null geometry to investigate the possibility of using deuterium (D) fuelling puff locations as an actuator for divertor argon (Ar) retention. Significant reduction of …
Preprint