O. Myatra B. Lipschultz D. Moulton K. Verhaegh B. Dudson S. Orchard A. Fil C. Cowley
Control of the detachment front between the target and the X-point is necessary for minimizing the effect of detachment on the core plasma (core radiation and loss of confinement) and maximizing the divertor functions (reduction of target heat load and sputtering, He pumping). However, such control has been difficult in experiments. The SOLPS-ITER …
PreprintJ. R. Harrison C. Bowman J. G. Clark A. Kirk B. S. Patel P. Ryan R. Scannell A. J. Thornton K. Verhaegh
The integration of good core and edge/pedestal confinement with strong dissipation of heat and particles in the divertors is a significant challenge for the development of fusion energy. Alternative divertor configurations offer potential advantages by broadening the operational space where a device can operate with detached divertors and acce…
PreprintC. Hill Dipti K. Heinola A. Dubois N. Sisourat A. Taoutioui H. Agueny K. Tokesi I. Ziaeian C. Illescas A. Jorge L. Mendez A. S. Kadyrov N. W. Antonio A. M. Kotian T. Kirchner A. C. K. Leung J. Ko J. K. Lee8 O. Marchuk M. G. O'Mullane E. Litherland-Smith G. I. Pokol O. Asztalos P. Balazs Y. Wu C. C. Jia L. Liu J. G. Wang
The injection of energetic neutral particles into the plasma of magnetic confinement fusion reactors is a widely-accepted method for heating such plasmas; various types of neutral beam are also used for diagnostic purposes. Accurate atomic data are required to properly model beam penetration into the plasma and to interpret photoemission spectra…
PublishedJ. Hobirk C. D. Challis A. Kappatou E. Lerche D. Keeling D. King S. Aleiferis E. Alessi F. Auriemma M. Baruzzo E. Belonohy I. S. Carvalho P. Carvalho F. J. Casson A. Chomiczewska J. Citrin I. H. Coffey D. Douai E. Delabie B. Eriksson J. Eriksson O. Ficker A. R. Field M. Fontana L. Frassinetti D. Frigione D. Gallart J. Garcia M. Gelfusa L. Giacomelli E. Giovannozzi C. Giroud M. Goniche C. Ham N. Hawkes R. Henriques J. Hillesheim A. Ho I. Ivanova-Stanik P. Jacquet F. Jaulmes E. Joffrin H. T. Kim V. Kiptily K. Kirov D. Kos E. Kowalska-Strzeciwilk H. Kumpulainen K. Lawson M. Lennholm X. Litaudon P. Lomas E. de la Luna C. Maggi J. Mailloux M. Mantsinen M. Maslov G. Matthews S. Menmuir A. Milocco K. McClements I. G. Miron S. Nowak F. Orsitto L. Piron G. Pucella E. Peluso C. Perez von Thun E. Rachlew C. Reux F. Rimini A. Sahlberg S. Saarelma P. A. Schneider M. Sertoli S. Sharapov S. Silburn A. Sips P. Siren E. Solano Z. Stancar C. Stuart H. Sun D. Valcarcel M. Valisa G. Verdoolaege N. Wendler D. Weston M. Zerbini
The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the ITER-like Be/W wall. The development started in pure Deuterium with refinement of the plasma current, and toroidal magnetic field choices and succeeded in solving the heat load challeng…
PublishedHJ. Sun T Wauters PJ. Lomas E. Lerche I. Monakhov C. Noble PC. De Vries K. Kirov I Coffey P Siren B Thomas A Boboc K Palamartchouk G Szepesi E. Joffrin B. Labit DC. McDonald JET Contributors
Ion Cyclotron wave (IC) assisted breakdown would be important for reducing risks to plasma initiation during the ITER pre-fusion operation phase under difficult vessel conditions. Hence, studies were performed at JET, at ITER relevant loop electric field — and in a regime, and , where plasma breakdown had not previously been achieved on JE…
Preprint PublishedI. Casiraghi P. Mantica F. Koechl R. Ambrosino B. Baiocchi A. Castaldo J. Citrin M. Dicorato L. Frassinetti A. Mariani P. Vincenzi P. Agostinetti L. Aucone L. Balbinot S. Ceccuzzi L. Figini G. Granucci P. Innocente T. Johnson H. Nyström M. Valisa
An intensive integrated modelling work of main scenarios of the new tokamak DTT (Divertor Tokamak Test facility) with the Single Null divertor configuration has been performed using first-principle quasi-linear transport models, in support to the design of the device and to the definition of its scientific work-programme. First results of this i…
PublishedHyun-Tae Kim F. Auriemma K. Kirov Z. Stancar R. Lorenzini J. Ferreira P. Huynh S. Gabriellini M. Poradzinski D. Gallart M. Nocente L. Garzotti C. Maggi M. Maslov F. Casson A. Di. Sienna J. Citrin P. Strand R. Gatto E. Tholerus E. Belli R. Sharma A. Osipov E. Fransson A. Kappatou C. D. Challis E. Lerche D. Eester J. Garcia JET contributors
2021 JET experimental campaign has produced high stationary fusion power with 50%D 50%T discharges, operated with the ITER-relevant conditions i.e. operation with the baseline or hybrid scenario in the full metallic wall. It has provided a unique opportunity to assess the DT fusion power prediction capability before ITER DT experiments. This paper …
Preprint PublishedL. Piron M. Baruzzo L. Baylor C. D. Challis M. P. Gryaznevich T. C. Hender R. B. Henriques N. Hawkes S. Jachmich E. Joffrin M. Lehnen M. Lennholm Y. Q. Liu J. Mailloux L. Moreira D. Valcarcel
This work describes the usage of Error Field Correction coil system [Barlow I. et al 2001 Fusion Eng. Des. 58-59 189], which is a set of 4 coils located external to the vessel of the JET device, with the aim of introducing non-axisymmetric n=1 magnetic field perturbations in various targeted plasma experiments. Besides being used to characterize…
PurchaseK. K. KIROV F. AURIEMMA P. J. BONOFIGLO C. D. CHALLIS E. DE LA LUNA J. ERIKSSON D. GALLART J. GARCIA M. GORELENKOVA J. HOBIRK P. JACQUET A. KAPPATOU Y. KAZAKOV D. KEELING D. KING V. KIPTILY E. LERCHE C. MAGGI J. MAILLOUX M. MASLOV M. MANTSINEN P. MANTICA S. MENMUIR R. SHARMA P. SIREN Z. STANCAR D. VAN EESTER JET CONTRIBUTORS
This work studies the influence of RF waves in ICRH range of frequency on fusion alphas during recent JET D-T campaign. Fusion alphas from D-T reactions are born with energies of about 3.5MeV and therefore have significant Doppler shift enabling synergistic interaction between them and RF waves at broad range of frequencies including the ones fo…
PreprintF.Eriksson E.Tholerus G.Corrigan Y.Baranov X.Bonnin D.Farina L.Figini L.Garzotti S.H.Kim F.Koechl A.Loarte E.Militello Asp C.Olde V.Parail S.D.Pinches A.Polevoi P.Strand
To design a safe termination scenario for a burning ITER plasma is a challenge that requires extensive core plasma and divertor modelling. The presented work consists of coupled core/edge/SOL/divertor simulations, performed with the JINTRAC code, studying the Q=10 flat-top phase and exit phase of the ITER 15MA/5.3T DT scenario. The modelling uti…
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