M. Mantsinen P. Jacquet E. Lerche D. Gallart K. Kirov P. Mantica D. Taylor D. Van Eester M. Baruzzo I. Carvalho C. Challis E. Delabie E. De La Luna R. Dumont P. Dumortier J. Eriksson D. Frigione J. Garcia L. Garzotti C. Giroud R. Henriques J. Hobirk A. Kappatou Y. Kazakov D. Keeling D. King V. Kiptily M. Lenholm P. Lomas C. Lowry C. Maggi J. Mailloux M. Maslov S. Menmuir I. Monakhov R.B. Morales C. Noble M. Nocente A. Patel G. Pucella C. Reux D. Rigamonti F. Rimini A. Sheikh S. Silburn P. Siren E. Solano Z. Stancar M. Tardochi
The reference ion cyclotron resonance frequency (ICRF) heating schemes for ITER deuterium-tritium (D-T) plasmas at the full magnetic field of 5.3 T are second harmonic heating of tritium and 3He minority heating. The wave-particle resonance location for these schemes coincide and are central at a wave frequency of 53 MHz at 5.3T [1]. Experiments ha…
PublishedK. K. Kirov E. Belonohy C. D. Challis J. Eriksson D. Frigione L. Garzotti L. Giacomelli J. Hobirk A. Kappatou D. Keeling D. King E. Lerche P. J. Lomas M. Nocente C. Reux F. G. Rimini A. C. C. Sips D. Van Eester JET Contributors
Achieving high neutron yields in today’s fusion research relies on high power auxiliary heating in order to attain required core temperatures. This is usually achieved by means of high Neutral Beam (NB) and Radio Frequency (RF) power. Application of NB power is accompanied by production of fast beam ions and associated Beam-Target (BT) reactio…
Preprint PublishedJ. Morris M. Y. Ye S. Mao
The Chinese Fusion Engineering Test Reactor (CFETR) bridges the gap between ITER and a demonstration fusion power plant (DEMO). The primary objectives of CFETR are: demonstrate tritium self-sufficiency, ~1GW fusion power, operate in steady-state and have a duty cycle of 0.3-0.5 [1]. CFETR is in the pre-conceptual design phase and is currently envis…
Preprint PublishedF. G. Rimini D. Alves G. Arnoux M. Baruzzo E. Belonohy I. Carvalho R. Felton E. Joffrin P. Lomas P. McCullen A. Neto I. Nunes C. Reux A. Stephen D. Valcarcel S. Wiesen JET EFDA contributors
The JET tokamak is unique amongst present fusion devices in its capability to operate at high plasma current, providing the closest plasma parameters to ITER. The physics benefits of high current operation have to be balanced against the risks to the integrity of the machine due to high force disruptions. The installation of the ITER-Like Wall (ILW…
Preprint PublishedL. Giacomelli S. Conroy F. Belli G. Gorini E. Joffrin V. Kiptily E. Lerche A. Murari V.V. Plyusnin S. Popovichev C. Reux M. Riva D.B. Syme JET EFDA Contributors
The Joint European Torus (JET, Culham, UK) is the largest tokamak in the world. 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 construction in Cadarache (France). At JET, the neutron emission profile of Deuterium (D) or Deuterium-Tritium (D…
PublishedP. C. De Vries M. Baruzzo G. M. D. Hogeweij S. Jachmich E. Joffrin P. J. Lomas G. F. Matthews A. Murari I. Nunes T. Pütterich C. Reux J. Vega JET-EFDA Contributors
In order to preserve the integrity of large tokamaks such as ITER, the number of disruptions has to be limited. JET has operated previously with a low frequency of disruptions (i.e., disruption rate) of 3.4% [P. C. de Vries et al., Nucl. Fusion 51, 053018 (2011)]. The start of operations with the new full-metal ITER-like wall at JET showed a marked…
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