X. 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 …
PreprintM. Valovič A. Boboc P. Carvalho I. Carvalho L. Garzotti F. Köchl J. C. Lowry S. Aleiferis C. Maggi P. Blatchford M. Fontdecaba Climent L. Frassinetti C. Olde R. B. Morales S. Nowak E. de la Luna F. Rimini Z. Stancar S. Silburn G. Tvalashvili M. Brix M. Vecsei D. Dunai D. Réfy the JET team
A dataset of baseline DT plasmas with peripheral HFS fuelling pellets has been produced on JET, in order to mimic the situtation in ITER. During the pellet ablation phase prompt particle losses due to pellet triggered ELM can be detected. Regarding pellet deposition, the data indicate that plasmoids drift velocity might be smaller than predicted…
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…
PreprintM. Kong E. Nardon M. Hoelzl D. Bonfiglio D. Hu U. Sheikh A. Boboc P. Carvalho T.C. Hender S. Jachmich K.D. Lawson S. Silburn Ž. Štancar R. Sweeney G. Szepesi the JOREK team JET contributors
Shattered pellet injection (SPI), with research started in recent years, is the current concept for the ITER disruption mitigation system (DMS) to prevent disruption-related damage. Compared with impurity SPI, pure deuterium (D2) SPI could contribute to runaway electron (RE) avoidance in ITER via a strong dilution cooling before the thermal quen…
PreprintN. VIANELLO N. WALKDEN M. DUNNE B. LOMANOWSKI E. WOLFRUM C. TSUI A. STAGNI M. GRIENER B. TAL T. EICH D. REFY D. BRIDA O. FEVRIER M. AGOSTINI H. DE OLIVEIRA S. ALEIFERIS M. BERNERT J. BOEDO M. BRIX D. CARRALERO I. CARVALHO L. FRASSINETTI C. GIROUD A. HAKOLA A. HUBER . KARHUNEN J, A. KARPUSHOV B. LABIT A. MEIGS V. NAULIN T. PEREIRA C. PEREZ VON THUN H. REIMERDES C. THEILER the ASDEX Upgrade Team the TCV team the EUROfusion MST1 Team the JET Contributors
The evolution of SOL density profiles and fluctuations have been studied at different recycling levels in 3 different tokamaks, ASDEXUpgrade, TCV and JET, all operated in HMode. In all devices we clearly observe an increase of far SOL efolding length at high …
Preprint PublishedH. Weisen C.F. Maggi M. Oberparleiter F.J. Casson S. Menmuir L Horvath F. Auriemma T.W. Bache N. Bonanomi Y. Camenen A. Chankin E. Delabie L. Frassinetti J. Garcia C. Giroud D. King R Lorenzini M. Marin P.A. Schneider P. Siren J. Varje E. Viezzer JET contributors
The isotope dependence of plasma transport has a significant impact on the performance of future D-T experiments in JET and ITER and eventually on the fusion gain and economics of future reactors. In preparation for future D-T operation on JET, dedicated experiments and comprehensive transport analysis were performed in H, D and H-D mixed plasma…
PreprintS.Pamela G.Huijsmans A.J.Thornton A.Kirk S.F.Smith M.Hoelzl T.Eich JET Contributors the MAST Team the JOREK Team
Typically applied to non-linear simulations of MHD instabilities relevant to magnetically confined fusion, the JOREK code was originally developed with a 2D grid composed of isoparametric bi-cubic Bezier finite elements, that are aligned to the magnetic equilibrium of tokamak plasmas. To improve the applicability of these simulations, the grid-gene…
Preprint PublishedS. S. Henderson M. Bernert S. Brezinsek M. Carr M. Cavedon R. Dux D. S. Gahle J. Harrison B. Lipschultz B. Lomanowski A. Meigs M. O’Mullane F. Reimold M. L. Reinke S. Wiesen the EUROfusion MST1 team the ASDEX Upgrade team JET contributors
Reducing the plasma power exhaust impacting on plasma facing components during steady state operation is one of the major design issues in future tokamaks such as ITER. Impurity seeding, e.g. with N, is one method of achieving this and has been used for a long time in tokamak research [1]. In this work we exploit a recently developed spectroscopic …
Preprint PublishedDL Keeling CD Challis I Jenkins NC Hawkes I Lupelli C Michael MFM. de Bock the MAST Team JET contributors
Experiments have been carried out on the MAST and JET tokamaks intended to compare the electrical resistivity of the plasma with theoretical formulations. The tests consist of obtaining motional stark effect (MSE) measurements in MHD-free plasmas during plasma current ramp-up (JET and MAST), ramp-down (MAST) and in stationary state (JET and MAST). …
Preprint PublishedS. C. Chapman P. T. Lang R. O. Dendy L. Giannone N. W. Watkins ASDEX 4 Upgrade Team
The ITER tokamak needs to sustain a plasma in a regime of high energy confinement (H-mode) to exceed fusion breakeven where power output exceeds input. H-mode plasmas are typically unstable to edge localised modes (ELMs), in which plasma escapes and strikes the plasma facing components. Scaled up to ITER, the energy released by ELMs can cause criti…
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