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

Journal Article · Wed May 29 00:00:00 EDT 2019 · Fusion Science and Technology

DOI:https://doi.org/10.1080/15361055.2019.1610314· OSTI ID:1558753

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

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

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.

• Research Organization: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
• Sponsoring Organization: USDOE
• Contributing Organization: NSTX-U Coil Test Team
• Grant/Contract Number: AC02-09CH11466
• OSTI ID: 1558753
• Journal Information: Fusion Science and Technology, Vol. 75, Issue 8; ISSN 1536-1055
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

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