Bus Design for the Poloidal Field Coils of the NSTX-Upgrade Fusion Device

Research output: Contribution to journalArticlepeer-review

Abstract

The National Spherical Torus eXperiment (NSTX) has undergone a major upgrade to NSTX-U at Princeton Plasma Physics Laboratory (PPPL). NSTX upgrade (NSTX-U) will double the toroidal field, plasma current, and neutral beam injection heating power, as well as significantly increase the pulse duration. NSTX-U uses three poloidal field (PF) coils at the vessel top and three at the bottom near the divertor areas to control the local plasma shape there. These shaping coils operate at a maximum terminal voltage of 2 kV, corresponding to a maximum current about 20 kA. To supply the power to the PF coils, hard copper bus bars are typically used near the vacuum vessel, while water cooled flexible cables are used away from the vessel. The detailed design of the hard copper bus bars will be covered in this article. During operation, these hard bus bars are subject to high electromagnetic (EM) forces, thermal displacement loads, as well as plasma halo loads due to disruption. The EM, thermal, and structural analysis were performed, and the results revealed that, with the worst loads combined, the new design meets the NSTX-U thermal, structural, and fatigue cycle requirements. The manufacturing and installation process of the bus work will be discussed at the end of this article.

Original languageEnglish (US)
Pages (from-to)4324-4329
Number of pages6
JournalIEEE Transactions on Plasma Science
Volume50
Issue number11
DOIs
StatePublished - Nov 1 2022

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Condensed Matter Physics

Keywords

  • Bus design
  • National Spherical Torus eXperiment upgrade (NSTX-U)
  • fusion structure
  • poloidal field (PF) coil

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