M-L. Mayoral V. Bobkov A. Czarnecka I. Day A. Ekedahl P. Jacquet M. Goniche R. King K. Kirov E. Lerche J. Mailloux D. Van Eester O. Asunta C. Challis D. Ciric J.W. Coenen L. Colas C. Giroud M. Graham I. Jenkins E. Joffrin T. Jones D.
The major aspects linked to the use of the JET auxiliary heating systems: NBI, ICRF and LHCD, in the new JET ITER-like wall (JET-ILW) are presented. We show that although there were issues related to the operation of each system, efficient and safe plasma heating was obtained with room for higher power. For the NBI up to 25.7MW was safely injected;…
PublishedGiacomelli L Conroy S Belli F Gorini G Horton L Joffrin E Lerche E Murari A Popovichev S Riva M Syme B JET EFDA Contributors
The Joint European Toras (JET, Culham, UK) is the largest tokamak in the world. It is devoted to nuclear fusion experiments of magnetic confined Deuterium (D) or Deuterium-Tritium (DT) plasmas. JET has been upgraded over the years and recently it has also become a test facility of the components designed for ITER, the next step fusion machine under…
PublishedP. Jacquet V. Bobkov S. Brezinsek M. Brix A-L. Campergue L. Colas A. Czarnecka P. Drewelow M. Graham C. C. Klepper E. Lerche M.-L. Mayoral A. Meigs D. Milanesio I. Monakhov J. Mlynar T. Pütterich A. Sirinelli D. Van-Eester JET-EFDA
In 2011/12, JET started operation with its new ITER-Like Wall (ILW) made of a tungsten (W) divertor and a beryllium (Be) main chamber wall. The impact of the new wall material on the JET Ion Cyclotron Resonance Frequency (ICRF) operation was assessed and also the properties of JET plasmas heated with ICRF were studied. No substantial change of the …
PublishedE. Lerche D. Van Eester Ph. Jacquet M.-L. Mayoral V. Bobkov L. Colas A. Czarnecka M. Graham G. Matthews I. Monakhov R. Neu T. Puetterich F. Rimini P. De Vries JET-EFDA Contributors
After the change over from the C-wall to the ITER-like Be/W wall (ILW) in JET, the radiation losses during ICRF heating have increased and are now substantially larger than those observed with NBI at the same power levels, in spite of the similar global plasma energies reached with the two heating systems. A comparison of the NBI and ICRF performan…
PublishedM.-L. Mayoral T. Pütterich P. Jacquet E. Lerche D. Van-Eester V. Bobkov C. Bourdelle L. Colas A. Czarnecka J. Mlynar R. Neu JET-EFDA Contributors
During the initial operation of the JET ITER-like wall, particular attention was given to the characterization of the Ion Cyclotron Resonance Frequency (ICRF) heating in this new metallic environment. In this contribution we compare L-modes plasmas heated by ICRF or by Neutral Beam Injection (NBI). ICRF heating as expected led to a much higher cent…
PublishedA. Czarnecka V. Bobkov I. H. Coffey L. Colas P. Jacquet K. D. Lawson E. Lerche C. Maggi M.-L. Mayoral T. Pütterich D. Van Eester JET-EFDA Contributors
Magnetically confined plasmas, such as those produced in the tokamak JET, contain measurable amounts of impurity ions produced during plasma-wall interactions (PWI) from the plasma-facing components and recessed wall areas. The impurities, including high- and mid-Z elements such as tungsten (W) from first wall tiles and nickel (Ni) from Inconel str…
PublishedD. Van Eester E. Lerche P. Jacquet V. Bobkov A. Czarnecka J. W. Coenen L. Colas K. Crombé M. Graham S. Jachmich E. Joffrin C. C. Klepper V. Kiptily M. Lehnen C. Maggi F. Marcotte G. Matthews M.-L. Mayoral K. McCormick I. Monakhov M. F. F. Nave, R. Neu, C. Noble, J. Ongena, T. Pütterich, F. Rimini, E. R. Solano, G. van Rooij, and JET-EFDA contributors
The most recent JET campaign has focused on characterizing operation with the "ITER-like" wall. One of the questions that needed to be answered is whether the auxiliary heating methods do not lead to unacceptably high levels of impurity influx, preventing fusion-relevant operation. In view of its high single pass absorption, hydrogen minority funda…
PublishedT. Franke E. Barbato A. Cardinali S. Ceccuzzi R. Cesario D. V. Eester E. Lerche M.-L. Mayoral F. Mirizzi M. Nightingale J.-M. Noterdaeme E. Poli A. A. Tuccillo R. Wenninger H. Zohm
The aim of driving a sufficient amount of plasma current with an appropriate radial current density profile is considered as one of the key challenges for a tokamak fusion power plant in steady state operation. Furthermore, efficient heating to enable transition to regime of enhanced confinement and to achieve breakeven plasma temperatures as well …
PublishedP. Jacquet F. Marcotte L. Colas G. Arnoux V. Bobkov Y. Corre S. Devaux J-L. Gardareine E. Gauthier M. Graham E. Lerche M-L. Mayoral I. Monakhov F.Rimini A. Sirinelli D. Van Eester JET EFDA Contributors
When using Ion Cyclotron Range of Frequency (ICRF) heating, enhanced heat-fluxes are commonly observed on some plasma facing components close to the antennas. Experiments have recently been carried out on JET with the new ITER-Like-Wall (ILW) to characterize the heat flux to the JET ICRF antennas. Using Infra-Red thermography and thermal models of …
PublishedD. Van Eester E. Lerche T. Johnson T. Hellsten J. Ongena et al.
The constructive interference effect described by Fuchs et al. [1] shows that the mode conversion and thereby the overall heating efficiency can be enhanced significantly when an integer number of fast wave wavelengths can be folded in between the high field side fast wave cutoff and the ion-ion hybrid layer(s) at which the ion Bernstein or ion cyc…
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