NSTX OH coil design improvements

M. Kalish; J. Chrzanowski; C. Neumeyer; B. Paul; R. Woolley; C. Jun

doi:10.1109/FUSION.2007.4337876

NSTX OH coil design improvements

M. Kalish, J. Chrzanowski, C. Neumeyer, B. Paul, R. Woolley, C. Jun

PPPL NSTX

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

Abstract

The National Spherical Torus Experiment (NSTX) has been operating successfully since February of 1999. A unique element of NSTX is the center solenoid or OH Coil that from the start has been a design challenged by the low aspect ratio/geometry of the device. To achieve this low aspect ratio the OH Coil's outer diameter is constrained to a narrow profile creating the need for creative design solutions concerning cooling connections, lead orientation, and insulation schemes. The original design has succeeded overall, but NSTX run time has been lost due to coil reliability issues. It was decided in the last year that it would be prudent to fabricate a new OH Coil and have it available as an upgrade to the experiment. The experience of operating and maintaining the OH Coil has provided the basis for an improved OH Coil design. A collaboration was arranged with ASIPP in China to fabricate a spare coil for NSTX. The new OH Coil will incorporate both design improvements intended to increase reliability as well as upgrades that will provide flexibility during future operation by allowing for an expanded operational profile. This paper summarizes and reviews these design and reliability improvements.

Original language	English (US)
Title of host publication	Proceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07
DOIs	https://doi.org/10.1109/FUSION.2007.4337876
State	Published - 2007
Event	22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07 - Albuquerque, NM, United States Duration: Jun 17 2007 → Jun 21 2007

Publication series

Name	Proceedings - Symposium on Fusion Engineering

Conference

Conference	22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07
Country/Territory	United States
City	Albuquerque, NM
Period	6/17/07 → 6/21/07

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering

Keywords

Fusion
NSTX
OH coil
Princeton plasma physics laboratory
Solenoid insulation

Access to Document

10.1109/FUSION.2007.4337876

Cite this

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title = "NSTX OH coil design improvements",

abstract = "The National Spherical Torus Experiment (NSTX) has been operating successfully since February of 1999. A unique element of NSTX is the center solenoid or OH Coil that from the start has been a design challenged by the low aspect ratio/geometry of the device. To achieve this low aspect ratio the OH Coil's outer diameter is constrained to a narrow profile creating the need for creative design solutions concerning cooling connections, lead orientation, and insulation schemes. The original design has succeeded overall, but NSTX run time has been lost due to coil reliability issues. It was decided in the last year that it would be prudent to fabricate a new OH Coil and have it available as an upgrade to the experiment. The experience of operating and maintaining the OH Coil has provided the basis for an improved OH Coil design. A collaboration was arranged with ASIPP in China to fabricate a spare coil for NSTX. The new OH Coil will incorporate both design improvements intended to increase reliability as well as upgrades that will provide flexibility during future operation by allowing for an expanded operational profile. This paper summarizes and reviews these design and reliability improvements.",

keywords = "Fusion, NSTX, OH coil, Princeton plasma physics laboratory, Solenoid insulation",

author = "M. Kalish and J. Chrzanowski and C. Neumeyer and B. Paul and R. Woolley and C. Jun",

year = "2007",

doi = "10.1109/FUSION.2007.4337876",

language = "English (US)",

isbn = "1424411947",

series = "Proceedings - Symposium on Fusion Engineering",

booktitle = "Proceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07",

note = "22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07 ; Conference date: 17-06-2007 Through 21-06-2007",

}

Kalish, M, Chrzanowski, J, Neumeyer, C, Paul, B, Woolley, R & Jun, C 2007, NSTX OH coil design improvements. in Proceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07., 4337876, Proceedings - Symposium on Fusion Engineering, 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07, Albuquerque, NM, United States, 6/17/07. https://doi.org/10.1109/FUSION.2007.4337876

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AU - Woolley, R.

AU - Jun, C.

PY - 2007

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N2 - The National Spherical Torus Experiment (NSTX) has been operating successfully since February of 1999. A unique element of NSTX is the center solenoid or OH Coil that from the start has been a design challenged by the low aspect ratio/geometry of the device. To achieve this low aspect ratio the OH Coil's outer diameter is constrained to a narrow profile creating the need for creative design solutions concerning cooling connections, lead orientation, and insulation schemes. The original design has succeeded overall, but NSTX run time has been lost due to coil reliability issues. It was decided in the last year that it would be prudent to fabricate a new OH Coil and have it available as an upgrade to the experiment. The experience of operating and maintaining the OH Coil has provided the basis for an improved OH Coil design. A collaboration was arranged with ASIPP in China to fabricate a spare coil for NSTX. The new OH Coil will incorporate both design improvements intended to increase reliability as well as upgrades that will provide flexibility during future operation by allowing for an expanded operational profile. This paper summarizes and reviews these design and reliability improvements.

AB - The National Spherical Torus Experiment (NSTX) has been operating successfully since February of 1999. A unique element of NSTX is the center solenoid or OH Coil that from the start has been a design challenged by the low aspect ratio/geometry of the device. To achieve this low aspect ratio the OH Coil's outer diameter is constrained to a narrow profile creating the need for creative design solutions concerning cooling connections, lead orientation, and insulation schemes. The original design has succeeded overall, but NSTX run time has been lost due to coil reliability issues. It was decided in the last year that it would be prudent to fabricate a new OH Coil and have it available as an upgrade to the experiment. The experience of operating and maintaining the OH Coil has provided the basis for an improved OH Coil design. A collaboration was arranged with ASIPP in China to fabricate a spare coil for NSTX. The new OH Coil will incorporate both design improvements intended to increase reliability as well as upgrades that will provide flexibility during future operation by allowing for an expanded operational profile. This paper summarizes and reviews these design and reliability improvements.

KW - Fusion

KW - NSTX

KW - OH coil

KW - Princeton plasma physics laboratory

KW - Solenoid insulation

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ER -

NSTX OH coil design improvements

Abstract

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All Science Journal Classification (ASJC) codes

Keywords

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