KSTAR poloidal and toroidal field design

B. J. Lee; N. Pomphrey; C. S. Chang; S. Y. Cho; S. C. Jardin; G. S. Lee; G. H. Neilson; H. Park; W. Reierson

KSTAR poloidal and toroidal field design

B. J. Lee, N. Pomphrey, C. S. Chang, S. Y. Cho, S. C. Jardin, G. S. Lee, G. H. Neilson, H. Park, W. Reierson

Research output: Contribution to conference › Paper › peer-review

Abstract

The Korean Superconducting Tokamak Advanced Research (KSTAR) will have superconducting magnets for both the poloidal field (PF) coils and the toroidal field (TF) coils. The physical arrangement of the PF set has 14 coils external to the TF coils. The analysis of the equilibrium flexibility of the KSTAR PF system determines the coil currents required to maintain prescribed equilibrium configurations over the desired range of operational parameters specified in I_p (q₉₅), β_N, and l₁(3). Constraints on the plasma separatrix and the flux linkage through the geometric center of the plasma are specified for the free boundary equilibrium calculations. In order to eliminate the remaining freedoms the coil current distribution is regularized (smoothed) by minimizing the quantity ncoil/∑/j=1) (Ij/ΔAj)² where ΔAj is the area of each PF coil. The ripple magnitude due to the finite number of TF coils and the size of the port for the neutral beam injector determine the number, size, and shape of TF coils. Two ripple criteria for a shaped plasma are used for types of ripple transport. The current design of the TF coil, 16 coils and D-shape, is big enough to satisfy requirements on the ripple magnitude at the plasma and to provide an adequate access for tangential NB injection.

Original language	English (US)
Pages	641-644
Number of pages	4
State	Published - 1998
Externally published	Yes
Event	Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) - San Diego, CA, USA Duration: Oct 6 1997 → Oct 10 1997

Other

Other	Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2)
City	San Diego, CA, USA
Period	10/6/97 → 10/10/97

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering

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title = "KSTAR poloidal and toroidal field design",

abstract = "The Korean Superconducting Tokamak Advanced Research (KSTAR) will have superconducting magnets for both the poloidal field (PF) coils and the toroidal field (TF) coils. The physical arrangement of the PF set has 14 coils external to the TF coils. The analysis of the equilibrium flexibility of the KSTAR PF system determines the coil currents required to maintain prescribed equilibrium configurations over the desired range of operational parameters specified in Ip (q95), βN, and l1(3). Constraints on the plasma separatrix and the flux linkage through the geometric center of the plasma are specified for the free boundary equilibrium calculations. In order to eliminate the remaining freedoms the coil current distribution is regularized (smoothed) by minimizing the quantity ncoil/∑/j=1) (Ij/ΔAj)2 where ΔAj is the area of each PF coil. The ripple magnitude due to the finite number of TF coils and the size of the port for the neutral beam injector determine the number, size, and shape of TF coils. Two ripple criteria for a shaped plasma are used for types of ripple transport. The current design of the TF coil, 16 coils and D-shape, is big enough to satisfy requirements on the ripple magnitude at the plasma and to provide an adequate access for tangential NB injection.",

author = "Lee, \{B. J.\} and N. Pomphrey and Chang, \{C. S.\} and Cho, \{S. Y.\} and Jardin, \{S. C.\} and Lee, \{G. S.\} and Neilson, \{G. H.\} and H. Park and W. Reierson",

year = "1998",

language = "English (US)",

pages = "641--644",

note = "Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) ; Conference date: 06-10-1997 Through 10-10-1997",

}

TY - CONF

T1 - KSTAR poloidal and toroidal field design

AU - Lee, B. J.

AU - Pomphrey, N.

AU - Chang, C. S.

AU - Cho, S. Y.

AU - Jardin, S. C.

AU - Lee, G. S.

AU - Neilson, G. H.

AU - Park, H.

AU - Reierson, W.

PY - 1998

Y1 - 1998

N2 - The Korean Superconducting Tokamak Advanced Research (KSTAR) will have superconducting magnets for both the poloidal field (PF) coils and the toroidal field (TF) coils. The physical arrangement of the PF set has 14 coils external to the TF coils. The analysis of the equilibrium flexibility of the KSTAR PF system determines the coil currents required to maintain prescribed equilibrium configurations over the desired range of operational parameters specified in Ip (q95), βN, and l1(3). Constraints on the plasma separatrix and the flux linkage through the geometric center of the plasma are specified for the free boundary equilibrium calculations. In order to eliminate the remaining freedoms the coil current distribution is regularized (smoothed) by minimizing the quantity ncoil/∑/j=1) (Ij/ΔAj)2 where ΔAj is the area of each PF coil. The ripple magnitude due to the finite number of TF coils and the size of the port for the neutral beam injector determine the number, size, and shape of TF coils. Two ripple criteria for a shaped plasma are used for types of ripple transport. The current design of the TF coil, 16 coils and D-shape, is big enough to satisfy requirements on the ripple magnitude at the plasma and to provide an adequate access for tangential NB injection.

AB - The Korean Superconducting Tokamak Advanced Research (KSTAR) will have superconducting magnets for both the poloidal field (PF) coils and the toroidal field (TF) coils. The physical arrangement of the PF set has 14 coils external to the TF coils. The analysis of the equilibrium flexibility of the KSTAR PF system determines the coil currents required to maintain prescribed equilibrium configurations over the desired range of operational parameters specified in Ip (q95), βN, and l1(3). Constraints on the plasma separatrix and the flux linkage through the geometric center of the plasma are specified for the free boundary equilibrium calculations. In order to eliminate the remaining freedoms the coil current distribution is regularized (smoothed) by minimizing the quantity ncoil/∑/j=1) (Ij/ΔAj)2 where ΔAj is the area of each PF coil. The ripple magnitude due to the finite number of TF coils and the size of the port for the neutral beam injector determine the number, size, and shape of TF coils. Two ripple criteria for a shaped plasma are used for types of ripple transport. The current design of the TF coil, 16 coils and D-shape, is big enough to satisfy requirements on the ripple magnitude at the plasma and to provide an adequate access for tangential NB injection.

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M3 - Paper

AN - SCOPUS:0031643125

SP - 641

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T2 - Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2)

Y2 - 6 October 1997 through 10 October 1997

ER -

KSTAR poloidal and toroidal field design

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