Superconducting poloidal field magnet engineering for the ARIES-ST

Leslie Bromberg; S. Pourrahimi; J. H. Schultz; P. Titus; S. Jardin; C. Kessel; W. Reiersen

doi:10.1016/S0920-3796(02)00309-5

Superconducting poloidal field magnet engineering for the ARIES-ST

Leslie Bromberg
, S. Pourrahimi
, J. H. Schultz
, P. Titus
, S. Jardin
, C. Kessel
, W. Reiersen

PPPL Theory

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

7 Scopus citations

Abstract

The critical issues of the poloidal systems for the ARIES-ST design have been presented in this paper. Because of the large plasma current and the need of highly shaped plasmas, the poloidal field (PF) coils should be located inside the toroidal field in order to reduce their current. Even then, the divertor coils carry large currents. The ARIES-ST PF coils are superconducting using the internally cooled cable-in-conduit conductor. The peak self field in the divertor coils is about 15 T and the highest field in the non-divertor coils is about 6 T. The PF magnets have built-in margins that are sufficient to survive disruptions without quenching. The costing study indicates that the specific cost of the PF system is $80/kg. Detailed design and trade-off studies of ARIES-ST are presented and remaining R&D issues are identified.

Original language	English (US)
Pages (from-to)	323-338
Number of pages	16
Journal	Fusion Engineering and Design
Volume	65
Issue number	2
DOIs	https://doi.org/10.1016/S0920-3796(02)00309-5
State	Published - Feb 2003

All Science Journal Classification (ASJC) codes

Civil and Structural Engineering
Nuclear Energy and Engineering
General Materials Science
Mechanical Engineering

Keywords

Plasma current
Poloidal field systems
Toroidal field

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10.1016/S0920-3796(02)00309-5

Cite this

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title = "Superconducting poloidal field magnet engineering for the ARIES-ST",

abstract = "The critical issues of the poloidal systems for the ARIES-ST design have been presented in this paper. Because of the large plasma current and the need of highly shaped plasmas, the poloidal field (PF) coils should be located inside the toroidal field in order to reduce their current. Even then, the divertor coils carry large currents. The ARIES-ST PF coils are superconducting using the internally cooled cable-in-conduit conductor. The peak self field in the divertor coils is about 15 T and the highest field in the non-divertor coils is about 6 T. The PF magnets have built-in margins that are sufficient to survive disruptions without quenching. The costing study indicates that the specific cost of the PF system is \$80/kg. Detailed design and trade-off studies of ARIES-ST are presented and remaining R\&D issues are identified.",

keywords = "Plasma current, Poloidal field systems, Toroidal field",

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TY - JOUR

T1 - Superconducting poloidal field magnet engineering for the ARIES-ST

AU - Bromberg, Leslie

AU - Pourrahimi, S.

AU - Schultz, J. H.

AU - Titus, P.

AU - Jardin, S.

AU - Kessel, C.

AU - Reiersen, W.

PY - 2003/2

Y1 - 2003/2

N2 - The critical issues of the poloidal systems for the ARIES-ST design have been presented in this paper. Because of the large plasma current and the need of highly shaped plasmas, the poloidal field (PF) coils should be located inside the toroidal field in order to reduce their current. Even then, the divertor coils carry large currents. The ARIES-ST PF coils are superconducting using the internally cooled cable-in-conduit conductor. The peak self field in the divertor coils is about 15 T and the highest field in the non-divertor coils is about 6 T. The PF magnets have built-in margins that are sufficient to survive disruptions without quenching. The costing study indicates that the specific cost of the PF system is $80/kg. Detailed design and trade-off studies of ARIES-ST are presented and remaining R&D issues are identified.

AB - The critical issues of the poloidal systems for the ARIES-ST design have been presented in this paper. Because of the large plasma current and the need of highly shaped plasmas, the poloidal field (PF) coils should be located inside the toroidal field in order to reduce their current. Even then, the divertor coils carry large currents. The ARIES-ST PF coils are superconducting using the internally cooled cable-in-conduit conductor. The peak self field in the divertor coils is about 15 T and the highest field in the non-divertor coils is about 6 T. The PF magnets have built-in margins that are sufficient to survive disruptions without quenching. The costing study indicates that the specific cost of the PF system is $80/kg. Detailed design and trade-off studies of ARIES-ST are presented and remaining R&D issues are identified.

KW - Plasma current

KW - Poloidal field systems

KW - Toroidal field

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UR - https://www.scopus.com/pages/publications/0037320522#tab=citedBy

U2 - 10.1016/S0920-3796(02)00309-5

DO - 10.1016/S0920-3796(02)00309-5

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Superconducting poloidal field magnet engineering for the ARIES-ST

Abstract

All Science Journal Classification (ASJC) codes

Keywords

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