The ITER central solenoid

Joel H. Schultz; Timothy Antaya; Jun Feng; Chen Yu Gung; Nicolai Martovetsky; Joseph V. Minervini; Philip Michael; Alexi Radovinsky; Peter Titus

doi:10.1109/FUSION.2005.252874

The ITER central solenoid

Joel H. Schultz, Timothy Antaya, Jun Feng, Chen Yu Gung, Nicolai Martovetsky, Joseph V. Minervini, Philip Michael, Alexi Radovinsky, Peter Titus

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

9 Scopus citations

Abstract

The Central Solenoid for the International Thermonuclear Experimental Reactor (ITER), a fusion tokamak experiment with the goal of generating 500 MW of fusion power with high gain (Q>10), must provide most of the volt-seconds needed to induce and sustain a 15 MA plasma for burn times of > 400 s. The 6.4 GJ Central Solenoid design requires a 45 kA conductor and has a peak field of 13 T. The Central Solenoid consists of six pancake-wound modules, stacked vertically, and held in axial compression by an external structure. The five-stage cable has 1/3 copper and 2/3 advanced Nb3Sn strands in a thick superalloy conduit and is cooled by the forced-flow of supercritical helium through the cable space. Key design issues include the qualification of a conduit with adequate fatigue strength, avoiding filament damage from transverse Lorentz loads, eliminating axial tension in the winding insulation, and qualification of space-saving intramodule butt joints.

Original language	English (US)
Title of host publication	21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05
Publisher	Institute of Electrical and Electronics Engineers Inc.
ISBN (Print)	142440150X, 9781424401505
DOIs	https://doi.org/10.1109/FUSION.2005.252874
State	Published - 2005
Externally published	Yes
Event	21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05 - Knoxville, TN, United States Duration: Sep 26 2005 → Sep 29 2005

Publication series

Name	Proceedings - Symposium on Fusion Engineering

Conference

Conference	21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05
Country/Territory	United States
City	Knoxville, TN
Period	9/26/05 → 9/29/05

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering

Keywords

Cable in conduit
Fusion reactors
ITER
Superconducting magnets
Superconductors

Access to Document

10.1109/FUSION.2005.252874

Cite this

Schultz, J. H., Antaya, T., Feng, J., Gung, C. Y., Martovetsky, N., Minervini, J. V., Michael, P., Radovinsky, A., & Titus, P. (2005). The ITER central solenoid. In 21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05 Article 4018908 (Proceedings - Symposium on Fusion Engineering). Institute of Electrical and Electronics Engineers Inc.. https://doi.org/10.1109/FUSION.2005.252874

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title = "The ITER central solenoid",

abstract = "The Central Solenoid for the International Thermonuclear Experimental Reactor (ITER), a fusion tokamak experiment with the goal of generating 500 MW of fusion power with high gain (Q>10), must provide most of the volt-seconds needed to induce and sustain a 15 MA plasma for burn times of > 400 s. The 6.4 GJ Central Solenoid design requires a 45 kA conductor and has a peak field of 13 T. The Central Solenoid consists of six pancake-wound modules, stacked vertically, and held in axial compression by an external structure. The five-stage cable has 1/3 copper and 2/3 advanced Nb3Sn strands in a thick superalloy conduit and is cooled by the forced-flow of supercritical helium through the cable space. Key design issues include the qualification of a conduit with adequate fatigue strength, avoiding filament damage from transverse Lorentz loads, eliminating axial tension in the winding insulation, and qualification of space-saving intramodule butt joints.",

keywords = "Cable in conduit, Fusion reactors, ITER, Superconducting magnets, Superconductors",

author = "Schultz, \{Joel H.\} and Timothy Antaya and Jun Feng and Gung, \{Chen Yu\} and Nicolai Martovetsky and Minervini, \{Joseph V.\} and Philip Michael and Alexi Radovinsky and Peter Titus",

year = "2005",

doi = "10.1109/FUSION.2005.252874",

language = "English (US)",

isbn = "142440150X",

series = "Proceedings - Symposium on Fusion Engineering",

publisher = "Institute of Electrical and Electronics Engineers Inc.",

booktitle = "21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05",

address = "United States",

note = "21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05 ; Conference date: 26-09-2005 Through 29-09-2005",

}

Schultz, JH, Antaya, T, Feng, J, Gung, CY, Martovetsky, N, Minervini, JV, Michael, P, Radovinsky, A & Titus, P 2005, The ITER central solenoid. in 21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05., 4018908, Proceedings - Symposium on Fusion Engineering, Institute of Electrical and Electronics Engineers Inc., 21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05, Knoxville, TN, United States, 9/26/05. https://doi.org/10.1109/FUSION.2005.252874

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T1 - The ITER central solenoid

AU - Schultz, Joel H.

AU - Antaya, Timothy

AU - Feng, Jun

AU - Gung, Chen Yu

AU - Martovetsky, Nicolai

AU - Minervini, Joseph V.

AU - Michael, Philip

AU - Radovinsky, Alexi

AU - Titus, Peter

PY - 2005

Y1 - 2005

N2 - The Central Solenoid for the International Thermonuclear Experimental Reactor (ITER), a fusion tokamak experiment with the goal of generating 500 MW of fusion power with high gain (Q>10), must provide most of the volt-seconds needed to induce and sustain a 15 MA plasma for burn times of > 400 s. The 6.4 GJ Central Solenoid design requires a 45 kA conductor and has a peak field of 13 T. The Central Solenoid consists of six pancake-wound modules, stacked vertically, and held in axial compression by an external structure. The five-stage cable has 1/3 copper and 2/3 advanced Nb3Sn strands in a thick superalloy conduit and is cooled by the forced-flow of supercritical helium through the cable space. Key design issues include the qualification of a conduit with adequate fatigue strength, avoiding filament damage from transverse Lorentz loads, eliminating axial tension in the winding insulation, and qualification of space-saving intramodule butt joints.

AB - The Central Solenoid for the International Thermonuclear Experimental Reactor (ITER), a fusion tokamak experiment with the goal of generating 500 MW of fusion power with high gain (Q>10), must provide most of the volt-seconds needed to induce and sustain a 15 MA plasma for burn times of > 400 s. The 6.4 GJ Central Solenoid design requires a 45 kA conductor and has a peak field of 13 T. The Central Solenoid consists of six pancake-wound modules, stacked vertically, and held in axial compression by an external structure. The five-stage cable has 1/3 copper and 2/3 advanced Nb3Sn strands in a thick superalloy conduit and is cooled by the forced-flow of supercritical helium through the cable space. Key design issues include the qualification of a conduit with adequate fatigue strength, avoiding filament damage from transverse Lorentz loads, eliminating axial tension in the winding insulation, and qualification of space-saving intramodule butt joints.

KW - Cable in conduit

KW - Fusion reactors

KW - ITER

KW - Superconducting magnets

KW - Superconductors

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U2 - 10.1109/FUSION.2005.252874

DO - 10.1109/FUSION.2005.252874

M3 - Conference contribution

AN - SCOPUS:34547747981

SN - 142440150X

SN - 9781424401505

T3 - Proceedings - Symposium on Fusion Engineering

BT - 21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05

PB - Institute of Electrical and Electronics Engineers Inc.

T2 - 21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05

Y2 - 26 September 2005 through 29 September 2005

ER -

The ITER central solenoid

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All Science Journal Classification (ASJC) codes

Keywords

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