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Overview of JET results
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
2011 (Engelska)Ingår i: Nuclear Fusion, ISSN 0029-5515, E-ISSN 1741-4326, Vol. 51, nr 9, s. 094008-Artikel i tidskrift (Refereegranskat) Published
Abstract [en]

Since the last IAEA Conference JET has been in operation for one year with a programmatic focus on the qualification of ITER operating scenarios, the consolidation of ITER design choices and preparation for plasma operation with the ITER-like wall presently being installed in JET. Good progress has been achieved, including stationary ELMy H-mode operation at 4.5 MA. The high confinement hybrid scenario has been extended to high triangularity, lower rho* and to pulse lengths comparable to the resistive time. The steady-state scenario has also been extended to lower rho* and nu* and optimized to simultaneously achieve, under stationary conditions, ITER-like values of all other relevant normalized parameters. A dedicated helium campaign has allowed key aspects of plasma control and H-mode operation for the ITER non-activated phase to be evaluated. Effective sawtooth control by fast ions has been demonstrated with (3)He minority ICRH, a scenario with negligible minority current drive. Edge localized mode (ELM) control studies using external n = 1 and n = 2 perturbation fields have found a resonance effect in ELM frequency for specific q(95) values. Complete ELM suppression has, however, not been observed, even with an edge Chirikov parameter larger than 1. Pellet ELM pacing has been demonstrated and the minimum pellet size needed to trigger an ELM has been estimated. For both natural and mitigated ELMs a broadening of the divertor ELM-wetted area with increasing ELM size has been found. In disruption studies with massive gas injection up to 50% of the thermal energy could be radiated before, and 20% during, the thermal quench. Halo currents could be reduced by 60% and, using argon/deuterium and neon/deuterium gas mixtures, runaway electron generation could be avoided. Most objectives of the ITER-like ICRH antenna have been demonstrated; matching with closely packed straps, ELM resilience, scattering matrix arc detection and operation at high power density (6.2 MW m(-2)) and antenna strap voltages (42 kV). Coupling measurements are in very good agreement with TOPICA modelling.

Ort, förlag, år, upplaga, sidor
2011. Vol. 51, nr 9, s. 094008-
Nyckelord [en]
Antennas, Fusion reactions, Helium, Pelletizing, Plasma confinement, Plasma theory, Scattering parameters
Nationell ämneskategori
Fusion, plasma och rymdfysik
Identifikatorer
URN: urn:nbn:se:kth:diva-41791DOI: 10.1088/0029-5515/51/9/094008ISI: 000294731600009Scopus ID: 2-s2.0-80052540664OAI: oai:DiVA.org:kth-41791DiVA, id: diva2:445248
Anmärkning

QC 20111003

Tillgänglig från: 2011-10-03 Skapad: 2011-10-03 Senast uppdaterad: 2020-04-21Bibliografiskt granskad

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Laxåback, Martin
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Fusionsplasmafysik
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Nuclear Fusion
Fusion, plasma och rymdfysik

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