Overview of JET results

Romanelli, F; Kamendje, R; Anda, G [Anda, Gábor (plazmafizika), szerző] Plazmafizikai Főosztály (KFKI RMKI); Dunai, D [Dunai, Dániel (plazmafizika), szerző] Plazmafizikai Főosztály (KFKI RMKI); Gál, K [Gál-Hobirk, Kinga Izabella (Plazmafizika), szerző] Plazmafizikai Főosztály (KFKI RMKI); Kálvin, S [Kálvin, Sándor Csaba, szerző] Plazmafizikai Főosztály (KFKI RMKI); Kocsis, G [Kocsis, Lajos Gábor (Plazmafizika, kva...), szerző] Plazmafizikai Főosztály (KFKI RMKI); Petravich, G [Petravich, Gábor Tamás (Plazmafizika), szerző] Plazmafizikai Főosztály (KFKI RMKI); Szepesi, T [Szepesi, Tamás Zoltán (plazmafizika), szerző]; Zoletnik, S [Zoletnik, Sándor (Plazmafizika), szerző] Plazmafizikai Főosztály (KFKI RMKI)

Angol nyelvű Tudományos Sokszerzős vagy csoportos szerzőségű szakcikk (Folyóiratcikk)
Megjelent: NUCLEAR FUSION 0029-5515 1741-4326 49 (10) Paper: 104006 2009
  • SJR Scopus - Condensed Matter Physics: D1
    Since the last IAEA conference, the scientific programme of JET has focused on the qualification of the integrated operating scenarios for ITER and on physics issues essential for the consolidation of design choices and the efficient exploitation of ITER. Particular attention has been given to the characterization of the edge plasma, pedestal energy and edge localized modes (ELMs), and their impact on plasma facing components (PFCs). Various ELM mitigation techniques have been assessed for all ITER operating scenarios using active methods such as resonant magnetic field perturbation, rapid variation of the radial field and pellet pacing. In particular, the amplitude and frequency of type I ELMs have been actively controlled over a wide parameter range (q(95) = 3-4.8, beta(N) <= 3.0) by adjusting the amplitude of the n = 1 external perturbation field induced by error field correction coils. The study of disruption induced heat loads on PFCs has taken advantage of a new wide-angle viewing infrared system and a fast bolometer to provide a detailed account of time, localization and form of the energy deposition. Specific ITER-relevant studies have used the unique JET capability of varying the toroidal field (TF) ripple from its normal low value delta(BT) = 0.08% up to delta(BT) = 1% to study the effect of TF ripple on high confinement-mode plasmas. The results suggest that delta(BT) < 0.5% is required on ITER to maintain adequate confinement to allow Q(DT) = 10 at full field. Physics issues of direct relevance to ITER include heat and toroidal momentum transport, with experiments using power modulation to decouple power input and torque to achieve first experimental evidence of inward momentum pinch in JET and determine the threshold for ion temperature gradient driven modes. Within the longer term JET programme in support of ITER, activities aiming at the modification of the JET first wall and divertor and the upgrade of the neutral beam and plasma control systems are being conducted. The procurement of all components will be completed by 2009 with the shutdown for the installation of the beryllium wall and tungsten divertor extending from summer 2009 to summer 2010.
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    2021-05-14 19:32