Results 121 to 130 of about 4,697,162 (157)

NSTX-U Control System Upgrades

Fusion Engineering and Design, 2014
AbstractThe National Spherical Tokamak Experiment (NSTX) is undergoing a wealth of upgrades (NSTX-U). These upgrades, especially including an elongated pulse length, require broad changes to the control system that has served NSTX well. A new fiber serial Front Panel Data Port input and output (I/O) stream will supersede the aging copper parallel ...
D A Gates, S P Gerhardt, P Sichta
exaly   +2 more sources

Control and Data Acquisition Upgrades for NSTX-U [PDF]

Fusion Engineering and Design, 2016
Abstract The extensive NSTX Upgrade (NSTX-U) Project includes major components which allow a doubling of the toroidal field strength to 1 T, of the Neutral Beam heating power to 12 MW, and the plasma current to 2 MA, and substantial structural enhancements to withstand the increased electromagnetic loads.
S P Gerhardt, P Sichta
exaly   +2 more sources

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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
openaire   +1 more source

Diagnostics for molybdenum and tungsten erosion and transport in NSTX-U

Review of Scientific Instruments, 2016
A comprehensive set of spectroscopic diagnostics is planned in the National Spherical Torus Experiment Upgrade to connect measurements of molybdenum and tungsten divertor sources to scrape-off layer (SOL) and core impurity transport, supporting the installation of high-Z plasma facing components which is scheduled to begin with a row of molybdenum ...
F, Scotti, V A, Soukhanovskii, M E, Weller   +2 more
openaire   +2 more sources

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
openaire   +1 more source

NSTX-U Construction Related Analysis Issues

Fusion Science and Technology, 2015
The National Spherical Torus Experiment Upgrade (NSTX-U) is currently under construction at Princeton Plasma Physics Laboratory (PPPL) It is scheduled to start operations early in 2015. Upgrade designs were analyzed and qualified prior to the beginning of construction, but many issues arose during manufacture and assembly that required adjustments in ...
Peter H. Titus*, L. Dudek, M. Smith, A. Brooks   +3 more
openaire   +1 more source

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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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
openaire   +1 more source

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