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Tungsten Measurement on Alcator C-Mod and EBIT for Future Fusion Reactors [PDF]
Barnard, H.S. +5 more
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MDSplus Current Developments and Future Directions [PDF]
, 2001 Fredian, Thomas, Stillerman, Joshua
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Development of CVD Diamond Detector for Particle Detector [PDF]
A. Chayahara +8 more
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Fast wave heating in the NSTX-Upgrade device
AIP Conference Proceedings, 2014NSTX-Upgrade will operate with toroidal magnetic fields (BT) up to 1 T, nearly twice the value used in the experiments on NSTX, and the available NBI power will be doubled. The doubling of BT while retaining the 30 MHz RF source frequency has moved the heating regime from the high harmonic fast wave (HHFW) regime used in NSTX to the mid harmonic fast ...
Nicola Bertelli +2 more
exaly +2 more sources
Center Stack Casing Bakeout BUS Design for the NSTX-Upgrade Fusion Device
Fusion Science and Technology, 2021Dang Cai, Peter H Titus, Chirag Rana
exaly +2 more sources
Bus Design for the Poloidal Field Coils of the NSTX-Upgrade Fusion Device
IEEE Transactions on Plasma Science, 2022Dang Cai, Jiarong Fang, Peter H Titus
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Wall Conditioning Systems for the NSTX-U Fusion Device
IEEE Transactions on Plasma Science, 2020Dang Cai
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Predicting HHFW Heating Efficiency on NSTX via Whole-Device Full-Wave Simulation
AIP Conference Proceedings, 2011We present a qualitative comparison of NSTX HHFW heating efficiency observations[1, 2] with results from the AORSA[3] whole‐device, linear simulation. The simulation retains a realistic geometry and core plasma kinetic physics such that scrape‐off plasma linear RF fields can be calculated. By examining L‐mode and neutral beam heated H‐mode scenarios we
D. L. Green +5 more
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