2016
DOI: 10.1016/j.fusengdes.2015.10.026
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Progress of JT-60SA Project: EU-JA joint efforts for assembly and fabrication of superconducting tokamak facilities and its research planning

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Cited by 23 publications
(9 citation statements)
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“…Being based on above the basic physics understanding of the H − beam non-uniformity in the QST 10A source, a super-giant H − source by multi-cusp arc-discharge has been developed for the N-NBI system of plasma heating and non-inductive current drive for the JT-60SA tokamak [24], which is currently one of the largest tokamaks with superconducting magnets in the world and now under construction as an EU-JAPAN international collaboration project.…”
Section: Modeling Of Qst Jt-60sa Kamaboko Sourcementioning
confidence: 99%
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“…Being based on above the basic physics understanding of the H − beam non-uniformity in the QST 10A source, a super-giant H − source by multi-cusp arc-discharge has been developed for the N-NBI system of plasma heating and non-inductive current drive for the JT-60SA tokamak [24], which is currently one of the largest tokamaks with superconducting magnets in the world and now under construction as an EU-JAPAN international collaboration project.…”
Section: Modeling Of Qst Jt-60sa Kamaboko Sourcementioning
confidence: 99%
“…For example, such a kind of non-uniformity was observed in the N-NBI system [20] for the JAEA (Japan Atomic Energy Research Agency: * present QST: National Institute for Quantum and Radiological Science and Technology) JT-60U tokamak. The JT-60U tokamak is one of the largest magnetic fusion devices in the world and now is being upgraded to the JT-60SA with superconducting magnets for plasma confinement [24].A series of modeling studies [25][26][27][28][29][30][31] for such giant sources, more specifically, for the QST 10A source and JT-60SA H − source will be reviewed (section 2.3). The effect of the EEDFs on H − SP and the origin of H − beam non-uniformity will be discussed.…”
mentioning
confidence: 99%
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“…Moreover, in this configuration the plasma needs to be sustained by a drive current that is particularly demanding due to the large toroidal plasma current and density and to the low value of the toroidal magnetic field. Also in conventional tokamaks, the inner part of the toroidal magnets and the ohmic transformer (solenoid) are crucial for any operation [4,11].…”
Section: Advantages and Potential Developments Of The Proto-sphera Apmentioning
confidence: 99%
“…The parameters of JT-60SA, as well as a description of the main plasma scenarios can be found in the JT-60SA Research Plan [2] and are summarized in tables 1 and 2. The most specific characteristics of the machine (size, shaping capability, pulse length, heating and current drive system, diagnostic and control systems) [3] qualify JT-60SA as a tokamak particularly suited for experimental investigation of high beta regimes, fast ion physics, control of high performance scenarios over long pulses [4]. Moreover, by a dedicated experimental programme, JT-60SA will be able to timely address specific ITER risk mitigation issues, such as disruption prevention and mitigation, runaways, ELM avoidance and control, L-H transition, mastering heat loads, test of high-priority diagnostics, real-time control strategies and event handling, etc.…”
Section: Introductionmentioning
confidence: 99%