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

doi:10.1016/j.fusengdes.2020.111900

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

ENG - Quantum Science and Energy Engineering

Research output: Contribution to journal › Article › peer-review

2 Citations (Scopus)

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 language	English
Article number	111900
Journal	Fusion Engineering and Design
Volume	161
DOIs	https://doi.org/10.1016/j.fusengdes.2020.111900
Publication status	Published - 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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10.1016/j.fusengdes.2020.111900

Cite this

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

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.",

keywords = "DEMO design, Error field, Error field correction coil, Superconducting magnet, Toroidal field coil",

author = "{Joint Special D esign Team for Fusion DEMO} and Hiroyasu Utoh and Go Matsunaga and Ryoji Hiwatari and Yoshiteru Sakamoto and Kenji Tobita",

note = "Funding Information: This work was carried out in the framework of the activity of the Joint Special Design Team for Fusion DEMO and partly by the DEMO Design Activity under the Broader Approach. Publisher Copyright: {\textcopyright} 2020 Elsevier B.V.",

year = "2020",

month = dec,

doi = "10.1016/j.fusengdes.2020.111900",

language = "English",

volume = "161",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

publisher = "Elsevier BV",

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TY - JOUR

T1 - Estimation of magnetic error field with alleviating fabrication tolerance of large superconducting magnets on JA DEMO reactor

AU - Joint Special D esign Team for Fusion DEMO

AU - Utoh, Hiroyasu

AU - Matsunaga, Go

AU - Hiwatari, Ryoji

AU - Sakamoto, Yoshiteru

AU - Tobita, Kenji

N1 - Funding Information: This work was carried out in the framework of the activity of the Joint Special Design Team for Fusion DEMO and partly by the DEMO Design Activity under the Broader Approach. Publisher Copyright: © 2020 Elsevier B.V.

PY - 2020/12

Y1 - 2020/12

N2 - 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.

AB - 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.

KW - DEMO design

KW - Error field

KW - Error field correction coil

KW - Superconducting magnet

KW - Toroidal field coil

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DO - 10.1016/j.fusengdes.2020.111900

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SN - 0920-3796

VL - 161

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

M1 - 111900

ER -

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

Abstract

Keywords

ASJC Scopus subject areas

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