Estimation of magnetic error field with alleviating fabrication tolerance of large superconducting magnets on JA DEMO reactor

Joint Special D esign Team for Fusion DEMO

Research output: Contribution to journalArticlepeer-review

Abstract

Generally, DEMO requires larger toroidal field (TF) coils than ITER, resulting in one of the major difficulties, the tolerance in TF coil fabrication. This paper presents the possible solutions based on the design study on Japan's DEMO (JA DEMO). It was confirmed that, in the case of adopting a mitigated tolerance by a factor of 2.5–5 compared with that of ITER, the resulting error field of TF coils is correctable to an acceptable level in terms of locked mode avoidance. In addition, the design of the error field correction coil (EFCC) on JA DEMO was investigated.

Original languageEnglish
Article number111900
JournalFusion Engineering and Design
Volume161
DOIs
Publication statusPublished - 2020 Dec

Keywords

  • DEMO design
  • Error field
  • Error field correction coil
  • Superconducting magnet
  • Toroidal field coil

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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