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Title: Scenario development during commissioning operations on the National Spherical Torus Experiment Upgrade

Journal Article · · Nuclear Fusion

The National Spherical Torus Experiment Upgrade (NSTX-U) will advance the physics basis required for achieving steady-state, high-beta, and high-confinement conditions in a tokamak by accessing high toroidal fields (1 T) and plasma currents (1.0–2.0 MA) in a low aspect ratio geometry (A = 1.6–1.8) with flexible auxiliary heating systems (12 MW NBI, 6 MW HHFW). This paper describes the progress in the development of L- and H-mode discharge scenarios and the commissioning of operational tools in the first ten weeks of operation that enable the scientific mission of NSTX-U. Vacuum field calculations completed prior to operations supported the rapid development and optimization of inductive breakdown at different values of ohmic solenoid current. The toroidal magnetic field (BT0 = 0.65 T) exceeded the maximum values achieved on NSTX and novel long-pulse L-mode discharges with regular sawtooth activity exceeded the longest pulses produced on NSTX (tpulse > 1.8 s). The increased flux of the central solenoid facilitated the development of stationary L-mode discharges over a range of density and plasma current (Ip). H-mode discharges achieved similar levels of stored energy, confinement (H98y,2 > 1) and stability (βNN-nowall > 1) compared to NSTX discharges for Ip ≤ 1 MA. High-performance H-mode scenarios require an L–H transition early in the Ip ramp-up phase in order to obtain low internal inductance (li) throughout the discharge, which is conducive to maintaining vertical stability at high elongation (κ > 2.2) and achieving long periods of MHD quiescent operations. Here, the rapid progress in developing L- and H-mode scenarios in support of the scientific program was enabled by advances in real-time plasma control, efficient error field identification and correction, effective conditioning of the graphite wall and excellent diagnostic availability.

Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States); Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Contributing Organization:
the NSTX-U Research, Operations and Engineering Team
Grant/Contract Number:
AC02-09CH11466; AC52-07NA27344
OSTI ID:
1425032
Alternate ID(s):
OSTI ID: 1771439
Report Number(s):
LLNL-JRNL-820541; TRN: US1802008
Journal Information:
Nuclear Fusion, Vol. 58, Issue 4; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 24 works
Citation information provided by
Web of Science

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Cited By (12)

Effect of deuterium irradiation on graphite boronized in the NSTX-U tokamak journal February 2019
Design and simulation of the snowflake divertor control for NSTX–U journal January 2019
Orbit modeling of fast particle redistribution induced by sawtooth instability journal July 2018
Divertor leg filaments in NSTX-U journal October 2018
NSTX/NSTX-U theory, modeling and analysis results journal June 2019
Real-time capable modeling of neutral beam injection on NSTX-U using neural networks journal March 2019
Initial transport and turbulence analysis and gyrokinetic simulation validation in NSTX-U L-mode plasmas journal April 2019
Investigation of fast particle redistribution induced by sawtooth instability in NSTX-U journal June 2019
Error field impact on mode locking and divertor heat flux in NSTX-U journal June 2019
Reduced model for direct induction startup scenario development on MAST-U and NSTX-U journal October 2019
Compact steady-state tokamak performance dependence on magnet and core physics limits journal February 2019
Scenario Development During Commissioning Operations on the National Spherical Torus Experiment Upgrade dataset January 2018