Results 1 to 10 of about 1,608 (195)
Advances in Boronization on NSTX-Upgrade
Nuclear Materials and Energy, 2017 Boronization has been effective in reducing plasma impurities and enabling access to higher density, higher confinement plasmas in many magnetic fusion devices. The National Spherical Torus eXperiment, NSTX, has recently undergone a major upgrade to NSTX-
Filippo Scotti, Felipe Bedoya, Dang Cai
exaly +5 more sources
Nonlinear gyrokinetic simulations of microtearing modes in NSTX and NSTX-U-like plasmas
Nuclear FusionA systematic nonlinear gyrokinetic analysis of microtearing modes (MTMs) in National Spherical Tokamak eXperiment (NSTX) discharges spanning high-, moderate-, and low-collisionality regimes around mid-radius is presented using the fully electromagnetic ...
Tajinder Singh +5 more
doaj +3 more sources
The NSTX trouble reporting system [PDF]
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231), 2003 An online Trouble Reporting System (TRS) has been introduced at the National Spherical Torus Experiment (NSTX). The TRS is used by NSTX operators to report problems that affect NSTX operations. The purpose of the TRS is to enhance NSTX reliability and maintainability by identifying components, occurrences, and trends that contribute to machine downtime.
S. Sengupta, G. Oliaro
core +5 more sources
The Use of MDSplus on NSTX at PPPL [PDF]
Fusion Engineering and Design, 2002 The MDSplus data acquisition system has been used successfully since the 1999 startup of NSTX [National Spherical Torus Experiment] for control, data acquisition, and analysis for diagnostic subsystems. For each plasma ''shot'' on NSTX about 75 MBs of data is acquired and loaded into MDSplus hierarchical data structures in 2-3 minutes.
P Roney, D Mastrovito, W Davis
exaly +3 more sources
, 2001 The National Spherical Torus Experiment (NSTX) has had a very productive period of plasma operations since the last ST Workshop in Seattle, WA, in November 1999. A number of new research tools have become available and the plasma parameters have improved significantly. These advances are describe in this paper.
Ono, M. +14 more
openaire +4 more sources
Nuclear Materials and Energy, 2018 Boronization is a Plasma Facing Component (PFC) conditioning technique widely used in tokamak machines. The National Spherical Torus Experiment-Upgrade (NSTX-U) applied this conditioning, using a plasma glow with a deuterated Trimethyl-boron (d-TMB) and ...
Filippo Scotti +2 more
exaly +3 more sources
Diagnostic Development on NSTX [PDF]
18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050), 1999 Diagnostics are described which are currently installed or under active development for the newly commissioned NSTX device. The low aspect ratio (R/a less than or equal to 1.3) and low toroidal field (0.1-0.3T) used in this device dictate adaptations in many standard diagnostic techniques.
Roquemore, A.L. +3 more
openaire +3 more sources
Diagnostics for the biased electrode experiment on NSTX [PDF]
Review of Scientific Instruments, 2008 A linear array of four small biased electrodes was installed in NSTX in an attempt to control the width of the scrape-off layer by creating a strong local poloidal electric field. The set of electrodes was separated poloidally by a 1 cm gap between electrodes and were located slightly below the midplane of NSTX, 1 cm behind the rf antenna, and oriented
A.L. Roquemore +5 more
openaire +2 more sources
Global modeling of wall material migration following boronization in NSTX-U
Nuclear Materials and Energy, 2019 Boronization is commonly utilized in tokamaks to suppress intrinsic impurities, most notably oxygen from residual water vapor. However, this is a temporary solution, as oxygen levels typically return to pre-boronization levels following repeated plasma ...
J.H. Nichols +6 more
doaj +1 more source
EPJ Web of Conferences, 2017 30 MHz fast-wave heating may be an effective tool for non-inductively ramping low-current plasmas to a level suitable for initiating up to 12 MW of neutral beam injection on the National Spherical Tokamak Experiment Upgrade (NSTX-U).
Taylor Gary +8 more
doaj +1 more source