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Completion of JT-60SA construction and contribution to ITER

  • the JT-60SA Integrated Project Team
  • National Institutes for Quantum and Radiological Science and Technology
  • Fusion for Energy
  • Commissariat à l'Énergie Atomique et aux Énergies Alternatives
  • CNR
  • National Institute for Fusion Science
  • EUROfusion
  • University of Seville
  • QST
  • Consorzio Rfx
  • Fusion for Energy
  • Culham Centre for Fusion Energy
  • Istituto di Fisica del Plasma Piero Caldirola
  • ENEA Centro Ricerche Frascati
  • CIEMAT
  • Institute of Plasma Physics, Academy of Sciences of the Czech Republic
  • Institute of Plasma Physics and Laser Microfusion
  • Centre de recherches en physique des plasmas
  • IST
  • STUDIECENTRUM VOOR KERNENERGIE / CENTRE D'ETUDE DE L'ENERGIE NUCLEAIRE
  • Karlsruher Institut für Technologie
  • Consorzio CREATE
  • Max Planck Institute for Plasma Physics
  • University of Tokyo
  • University of Tsukuba
  • Nagoya University
  • Osaka University
  • Tottori University
  • Universitat Politècnica de Catalunya (UPC)
  • Kyushu University
  • Fukui University of Technology
  • Keio University
  • Tokyo Institute of Technology
  • Tohoku University
  • Kyoto University
  • EK Egyesulet
  • Aalto University
  • ITER
  • University of Napoli 'Federico II'
  • CNR-IFAC
  • Hokkaido University
  • Shizuoka University
  • University of Tuscia
  • Kyoto Institute of Technology
  • National Institute of Technology, Gifu College
  • IAP
  • FORSCHUNGSZENTRUM JULICH GMBH

Onderzoeksoutput: Bijdrage aan een tijdschriftArtikelpeer review

60 Citaten (Scopus)

Samenvatting

Construction of the JT-60SA tokamak was completed on schedule in March 2020. Manufacture and assembly of all the main tokamak components satisfied technical requirements, including dimensional accuracy and functional performances. Development of the plasma heating systems and diagnostics have also progressed, including the demonstration of the favourable electron cyclotron range of frequency (ECRF) transmission at multiple frequencies and the achievement of long sustainment of a high-energy intense negative ion beam. Development of all the tokamak operation control systems has been completed, together with an improved plasma equilibrium control scheme suitable for superconducting tokamaks including ITER. For preparation of the tokamak operation, plasma discharge scenarios have been established using this advanced equilibrium controller. Individual commissioning of the cryogenic system and the power supply system confirmed that these systems satisfy design requirements including operational schemes contributing directly to ITER, such as active control of heat load fluctuation of the cryoplant, which is essential for dynamic operation in superconducting tokamaks. The integrated commissioning (IC) is started by vacuum pumping of the vacuum vessel and cryostat, and then moved to cool-down of the tokamak and coil excitation tests. Transition to the super-conducting state was confirmed for all the TF, EF and CS coils. The TF coil current successfully reached 25.7 kA, which is the nominal operating current of the TF coil. For this nominal toroidal field of 2.25 T, ECRF was applied and an ECRF plasma was created. The IC was, however, suspended by an incident of over current of one of the superconducting equilibrium field coil and He leakage caused by insufficient voltage holding capability at a terminal joint of the coil. The unique importance of JT-60SA for H-mode and high-β steady-state plasma research has been confirmed using advanced integrated modellings. These experiences of assembly, IC and plasma operation of JT-60SA contribute to ITER risk mitigation and efficient implementation of ITER operation.

Originele taal-2Engels
Artikelnummer042002
TijdschriftNuclear Fusion
Volume62
Nummer van het tijdschrift4
DOI's
StatusGepubliceerd - apr. 2022

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