Prototype Coil Evaluation for NSTX-U Replacement Inner Poloidal Field Coils

Zhai, Y.; Neumeyer, C.; Dellas, J.; Greenough, N.; Kalish, M.; Petrella, J.; Que, W.; Raftopoulos, S.

doi:10.1080/15361055.2019.1610314

Title: Prototype Coil Evaluation for NSTX-U Replacement Inner Poloidal Field Coils

Abstract

The National Spherical Torus eXperiment Upgrade (NSTX-U) is an innovative magnetic fusion device constructed at the Princeton Plasma Physics Laboratory (PPPL). In 2016, because of the failure of the PF-1a upper divertor coil, which experienced a coolant blockage, the NSTX-U operation was suspended. A postmortem investigation indicated that an undetected gradual deterioration of coil inductance preceded the coolant blockage leading up to the operational suspension. The project team decided that all inner poiloidal field (PF) upper and lower coil pairs, denoted PF-1a, PF-1b, and PF-1c, shall be replaced with new coils of improved design and manufacture. Here, the new prototype inner PF coils from four suppliers across the globe were evaluated at PPPL following a prototype technical evaluation procedure. Mechanical inspection and electrical testing were performed to qualify each supplier.

Authors:

Zhai, Y. ^[1]; Neumeyer, C. ^[1]; Dellas, J. ^[1]; Greenough, N. ^[1]; Kalish, M. ^[1]; Petrella, J. ^[1]; Que, W. ^[1]; Raftopoulos, S. ^[1]

Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Publication Date:: Wed May 29 00:00:00 EDT 2019

Research Org.:: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Sponsoring Org.:: USDOE

Contributing Org.:: NSTX-U Coil Test Team

OSTI Identifier:: 1558753

Grant/Contract Number:: AC02-09CH11466

Resource Type:: Accepted Manuscript

Journal Name:: Fusion Science and Technology

Additional Journal Information:: Journal Volume: 75; Journal Issue: 8; Journal ID: ISSN 1536-1055

Publisher:: American Nuclear Society

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; NSTX-U; fusion magnets; poloidal field coils; prototype; coil testing

Citation Formats


                    Zhai, Y., Neumeyer, C., Dellas, J., Greenough, N., Kalish, M., Petrella, J., Que, W., and Raftopoulos, S. Prototype Coil Evaluation for NSTX-U Replacement Inner Poloidal Field Coils.  United States: N. p., 2019. 
Web.  doi:10.1080/15361055.2019.1610314.

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                    Zhai, Y., Neumeyer, C., Dellas, J., Greenough, N., Kalish, M., Petrella, J., Que, W., & Raftopoulos, S. Prototype Coil Evaluation for NSTX-U Replacement Inner Poloidal Field Coils.  United States.  https://doi.org/10.1080/15361055.2019.1610314

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                    Zhai, Y., Neumeyer, C., Dellas, J., Greenough, N., Kalish, M., Petrella, J., Que, W., and Raftopoulos, S. Wed .  
"Prototype Coil Evaluation for NSTX-U Replacement Inner Poloidal Field Coils".  United States.  https://doi.org/10.1080/15361055.2019.1610314.  https://www.osti.gov/servlets/purl/1558753.

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@article{osti_1558753,

  title        = {Prototype Coil Evaluation for NSTX-U Replacement Inner Poloidal Field Coils},

  author       = {Zhai, Y. and Neumeyer, C. and Dellas, J. and Greenough, N. and Kalish, M. and Petrella, J. and Que, W. and Raftopoulos, S.},

  abstractNote = {The National Spherical Torus eXperiment Upgrade (NSTX-U) is an innovative magnetic fusion device constructed at the Princeton Plasma Physics Laboratory (PPPL). In 2016, because of the failure of the PF-1a upper divertor coil, which experienced a coolant blockage, the NSTX-U operation was suspended. A postmortem investigation indicated that an undetected gradual deterioration of coil inductance preceded the coolant blockage leading up to the operational suspension. The project team decided that all inner poiloidal field (PF) upper and lower coil pairs, denoted PF-1a, PF-1b, and PF-1c, shall be replaced with new coils of improved design and manufacture. Here, the new prototype inner PF coils from four suppliers across the globe were evaluated at PPPL following a prototype technical evaluation procedure. Mechanical inspection and electrical testing were performed to qualify each supplier.},

  doi          = {10.1080/15361055.2019.1610314},

  journal      = {Fusion Science and Technology},

  number       = 8,

  volume       = 75,

  place        = {United States},

  year         = {Wed May 29 00:00:00 EDT 2019},

  month        = {Wed May 29 00:00:00 EDT 2019}

}

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https://doi.org/10.1080/15361055.2019.1610314

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Works referenced in this record:

Overview of NSTX Upgrade initial results and modelling highlights
journal, June 2017

Menard, J. E.; Allain, J. P.; Battaglia, D. J.
Nuclear Fusion, Vol. 57, Issue 10, Article No. 102006
DOI: 10.1088/1741-4326/aa600a

Overview of the physics and engineering design of NSTX upgrade
journal, July 2012

Menard, J. E.; Gerhardt, S.; Bell, M.
Nuclear Fusion, Vol. 52, Issue 8
DOI: 10.1088/0029-5515/52/8/083015

Engineering design of the National Spherical Torus Experiment
journal, February 2001

Neumeyer, C.; Heitzenroeder, P.; Spitzer, J.
Fusion Engineering and Design, Vol. 54, Issue 2
DOI: 10.1016/S0920-3796(00)00469-5

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Title: Prototype Coil Evaluation for NSTX-U Replacement Inner Poloidal Field Coils

Abstract

Citation Formats

Overview of NSTX Upgrade initial results and modelling highlights journal, June 2017

Overview of the physics and engineering design of NSTX upgrade journal, July 2012

Engineering design of the National Spherical Torus Experiment journal, February 2001

Overview of NSTX Upgrade initial results and modelling highlights
journal, June 2017

Overview of the physics and engineering design of NSTX upgrade
journal, July 2012

Engineering design of the National Spherical Torus Experiment
journal, February 2001