Results 131 to 140 of about 670 (162)

NSTX-U Vacuum Vessel design modification

2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 2013
The NSTX-U requirements will double the Toroidal Field (TF), Plasma Current (Ip), Beam Injection Power, and extend pulse length. The larger centerstack requires re-aiming of the Multi Pulse Thomson Scattering (MPTS) lasers and Vacuum Vessel (VV) modifications at Bay L.
Neway D. Atnafu, M. Denault, L. Dudek, S. Gerhardt, G. Labik, M. Smith, T. Stevenson, P. Titus   +7 more
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Reconfigurable timing unit for NSTX-U

2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 2013
Due to the longer pulse length of the NSTX-U device, a significant portion of the CAMAC equipment used for data acquisition and control will be supplanted with instrumentation and control (I&C) technologies such as CompactPCI and PXI Express. The Timing and Synchronization System (T&S) is used to synchronize data acquisition and control throughout the ...
S. DeLuca, P. Sichta, G. Tchilinguirian
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Vacuum compatability of welded joints for NSTX-U

2011 IEEE/NPSS 24th Symposium on Fusion Engineering, 2011
The high vacuum environment of the National Spherical Torus Experiment (NSTX) cannot tolerate a leak rate of greater than 1×10−5 Torr-liters per second or an out-gassing rate of more than 2×10−12 Torr-liters per second per cm2. This is maintained with an austenitic 316 stainless steel vacuum vessel.
M. Denault, D. Arose
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Electrical Testing of NSTX-U Inner Poloidal Field Coils

IEEE Transactions on Plasma Science, 2021
The National Spherical Torus eXperiment—Upgrade (NSTX-U) experienced a series of technical problems during its initial operating campaign leading to an extended outage and recovery period. The final event that necessitated shutdown was a turn-to-turn fault in one of the inner PF coils.
C. Neumeyer, J. Dellas, N. Greenough, J. Petrella, W. Que, Y. Zhai   +5 more
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The NSTX-U Digital Coil Protection System Autotester

2015 IEEE 26th Symposium on Fusion Engineering (SOFE), 2015
Included in the Upgrade to NSTX at Princeton University's Plasma Physics Laboratory, is the development of a Digital Coil Protection System (DCPS). This real-time system is the primary protection for the machine coils and structure of the NSTX-U vessel.
Gretchen Zimmer, John Dong, Ronald E. Hatcher   +2 more
openaire   +1 more source

Massive Gas Injection Valve Development for NSTX-U

IEEE Transactions on Plasma Science, 2016
NSTX-U research will offer new insights by studying gas assimilation efficiencies for massive gas injection (MGI) from different poloidal locations using identical gas injection systems. In support of this activity, an electromagnetic MGI valve has been built and tested.
R. Raman, G. J. Plunkett, W.-S. Lay
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A poloidal high-k scattering system for NSTX-U

Journal of Instrumentation, 2022
Abstract A previous 5-channel tangential high-k scattering system is being replaced by an 8-channel, poloidal high-k scattering system on the National Spherical Torus eXperiment Upgrade (NSTX-U) device located in Princeton, NJ, USA. The 693 GHz poloidal scattering system replaces a 280 GHz tangential scattering system to study high-k ...
C.W. Domier, J. Dannenberg, Y. Zhu, X. Liu, J.R. Sirigiri, Y. Ren, B. Stratton, N.C. Luhmann   +7 more
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The high-k poloidal scattering system for NSTX-U

Review of Scientific Instruments, 2018
An 8-channel, high-k poloidal far-infrared (FIR) scattering system is under development for the National Spherical Torus eXperiment Upgrade (NSTX-U). The 693 GHz poloidal scattering system replaces a 5-channel, 280 GHz high-k toroidal scattering system to study high-k electron density fluctuations on NSTX-U.
R. Barchfeld, C. W. Domier, Y. Ren, R. Ellis, P. Riemenschneider, N. Allen, R. Kaita, B. Stratton, J. Dannenberg, Y. Zhu, N. C. Luhmann   +10 more
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Applicability of alkali beam emission spectroscopy on NSTX-U

Review of Scientific Instruments
Understanding fast pedestal dynamics and turbulent transport in the edge and scrape-off layer (SOL) plasma of spherical tokamaks is crucial for the design and operation of future fusion reactors. The alkali beam emission spectroscopy diagnostic technique offers a means to measure the absolute electron density radial profile and fluctuation amplitude in
M. Lampert, G. Anda, O. Asztalos, J. W. Berkery, A. Diallo, B. Stratton, S. Zoletnik   +6 more
openaire   +2 more sources

Progress toward commissioning and plasma operation in NSTX-U

Nuclear Fusion, 2015
The National Spherical Torus Experiment-Upgrade (NSTX-U) is the most powerful spherical torus facility at PPPL, Princeton USA. The major mission of NSTX-U is to develop the physics basis for an ST-based Fusion Nuclear Science Facility (FNSF). The ST-based FNSF has the promise of achieving the high neutron fluence needed for reactor component testing ...
M. Ono, J. Chrzanowski, L. Dudek, S. Gerhardt, P. Heitzenroeder, R. Kaita, J.E. Menard, E. Perry, T. Stevenson, R. Strykowsky, P. Titus, A. von Halle, M. Williams, N.D. Atnafu, W. Blanchard, M. Cropper, A. Diallo, D.A. Gates, R. Ellis, K. Erickson, J. Hosea, R. Hatcher, S.Z. Jurczynski, S. Kaye, G. Labik, J. Lawson, B. LeBlanc, R. Maingi, C. Neumeyer, R. Raman, S. Raftopoulos, R. Ramakrishnan, A.L. Roquemore, S.A. Sabbagh, P. Sichta, H. Schneider, M. Smith, B. Stratton, V. Soukhanovskii, G. Taylor, K. Tresemer, A. Zolfaghari   +41 more
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