Design study of superconducting coils for the fusion DEMO plant at JAERI

T. Isono; N. Koizumi; K. Okuno; R. Kurihara; S. Nishio; K. Tobita

doi:10.1016/j.fusengdes.2005.08.078

Design study of superconducting coils for the fusion DEMO plant at JAERI

T. Isono, N. Koizumi, K. Okuno, R. Kurihara, S. Nishio, K. Tobita

Research output: Contribution to journal › Conference article › peer-review

6 Citations (Scopus)

Abstract

A design study of the TF coil for the fusion DEMO plant at JAERI is in progress. A major issue is to estimate the maximum fields generated by the TF coils for three tokamak options and two conductor options. Three tokamak options are proposed varying the aspect ratio and the role of the CS coil. Two kinds of conductors using advanced superconducting materials are candidates for the TF coils: Nb₃Al and high temperature superconductor (HTS). In order to evaluate achievable magnetic fields, a simple method was adopted to calculate mechanical properties. The estimated maximum fields are 17-20 T by the HTS conductor and 16-17 T by the Nb₃Al conductor. There is a possibility of a 0.7 T enhancement using grading of Nb₃Al winding.

Original language	English
Pages (from-to)	1257-1261
Number of pages	5
Journal	Fusion Engineering and Design
Volume	81
Issue number	8-14 PART B
DOIs	https://doi.org/10.1016/j.fusengdes.2005.08.078
Publication status	Published - 2006 Feb
Externally published	Yes
Event	Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B - Duration: 2005 May 22 → 2005 May 27

Keywords

Fusion DEMO plant
HTS
NbAl
Superconducting 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.2005.08.078

Cite this

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title = "Design study of superconducting coils for the fusion DEMO plant at JAERI",

abstract = "A design study of the TF coil for the fusion DEMO plant at JAERI is in progress. A major issue is to estimate the maximum fields generated by the TF coils for three tokamak options and two conductor options. Three tokamak options are proposed varying the aspect ratio and the role of the CS coil. Two kinds of conductors using advanced superconducting materials are candidates for the TF coils: Nb3Al and high temperature superconductor (HTS). In order to evaluate achievable magnetic fields, a simple method was adopted to calculate mechanical properties. The estimated maximum fields are 17-20 T by the HTS conductor and 16-17 T by the Nb3Al conductor. There is a possibility of a 0.7 T enhancement using grading of Nb3Al winding.",

keywords = "Fusion DEMO plant, HTS, NbAl, Superconducting coil",

author = "T. Isono and N. Koizumi and K. Okuno and R. Kurihara and S. Nishio and K. Tobita",

year = "2006",

month = feb,

doi = "10.1016/j.fusengdes.2005.08.078",

language = "English",

volume = "81",

pages = "1257--1261",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

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number = "8-14 PART B",

note = "Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B ; Conference date: 22-05-2005 Through 27-05-2005",

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TY - JOUR

T1 - Design study of superconducting coils for the fusion DEMO plant at JAERI

AU - Isono, T.

AU - Koizumi, N.

AU - Okuno, K.

AU - Kurihara, R.

AU - Nishio, S.

AU - Tobita, K.

PY - 2006/2

Y1 - 2006/2

N2 - A design study of the TF coil for the fusion DEMO plant at JAERI is in progress. A major issue is to estimate the maximum fields generated by the TF coils for three tokamak options and two conductor options. Three tokamak options are proposed varying the aspect ratio and the role of the CS coil. Two kinds of conductors using advanced superconducting materials are candidates for the TF coils: Nb3Al and high temperature superconductor (HTS). In order to evaluate achievable magnetic fields, a simple method was adopted to calculate mechanical properties. The estimated maximum fields are 17-20 T by the HTS conductor and 16-17 T by the Nb3Al conductor. There is a possibility of a 0.7 T enhancement using grading of Nb3Al winding.

AB - A design study of the TF coil for the fusion DEMO plant at JAERI is in progress. A major issue is to estimate the maximum fields generated by the TF coils for three tokamak options and two conductor options. Three tokamak options are proposed varying the aspect ratio and the role of the CS coil. Two kinds of conductors using advanced superconducting materials are candidates for the TF coils: Nb3Al and high temperature superconductor (HTS). In order to evaluate achievable magnetic fields, a simple method was adopted to calculate mechanical properties. The estimated maximum fields are 17-20 T by the HTS conductor and 16-17 T by the Nb3Al conductor. There is a possibility of a 0.7 T enhancement using grading of Nb3Al winding.

KW - Fusion DEMO plant

KW - HTS

KW - NbAl

KW - Superconducting coil

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IS - 8-14 PART B

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Y2 - 22 May 2005 through 27 May 2005

ER -

Design study of superconducting coils for the fusion DEMO plant at JAERI

Abstract

Keywords

ASJC Scopus subject areas

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