Results 1 to 10 of about 1,237 (85)

Exploration of spherical torus physics in the NSTX device [PDF]

Nuclear Fusion, 2000
The National Spherical Torus Experiment (NSTX) is being built at the Princeton Plasma Physics Laboratory to test the fusion physics principles for the Spherical Torus (ST) concept at the MA level. The NSTX nominal plasma parameters are R {sub 0} = 85 cm, a = 67 cm, R/a greater than or equal to 1.26, B {sub T} = 3 kG, I {sub p} = 1 MA, q {sub 95} = 14 ...
Masayuki Ono, Stanley Kaye, David A Gates   +2 more
exaly   +4 more sources

Plasma Response to the Application of 30 MHz RF Power in the NSTX Device [PDF]

AIP Conference Proceedings, 2001
Radio-frequency power at 30 MHz has been applied in a variety of situations to National Spherical Torus Experiment (NSTX) plasmas. The response of the plasma is observed in order to study both the physics of High Harmonic Fast Wave (HHFW) heating and as a tool to extend the performance of NSTX plasmas. In this paper we will discuss the progress made to
Wilson, J. R., Bell, R. E., Bernabei, S., Hosea, J. C., LeBlanc, B. P., Mau, T. K., Menard, J., Ono, M., Paoletti, F., Pinsker, R., Phillips, C. K., Rosenberg, A., Ryan, P. M., Sabbagh, S., Stutman, D., Swain, D. W., Wilgen, J. B., Takase, Y.   +17 more
openaire   +3 more sources

Flowing liquid lithium plasma-facing components – Physics, technology and system analysis of the LiMIT system

Nuclear Materials and Energy, 2017
The use of low atomic number liquid metals has been shown to have the potential to solve many of the prevalent problems like erosion and radiation losses associated with the interaction of fusion plasma with the plasma facing component (PFC) structures ...
D.N. Ruzic, M. Szott, C. Sandoval, M. Christenson, P. Fiflis, S. Hammouti, K. Kalathiparambil, I. Shchelkanov, D. Andruczyk, R. Stubbers, C. Joel Foster, B. Jurczyk   +11 more
doaj   +1 more source

Self-consistent calculation of the effects of RF injection in the HHFW heating regimes on the evolution of fast ions in toroidal plasmas

EPJ Web of Conferences, 2017
A critical question for the use of ion cyclotron range of frequency (ICRF) heating in the ITER device and beyond is interaction of fast waves with energetic ion populations from neutral beam injection (NBI), fusion reactions, and minority ions ...
Bertelli Nicola, Gorelenkova Marina, Podesta Mario, Valeo Ernest, Green David, Fredrickson Eric   +5 more
doaj   +1 more source

Safety Analysis in Large Volume Vacuum Systems Like Tokamak: Experiments and Numerical Simulation to Analyze Vacuum Ruptures Consequences

Advances in Materials Science and Engineering, Volume 2014, Issue 1, 2014., 2014
The large volume vacuum systems are used in many industrial operations and research laboratories. Accidents in these systems should have a relevant economical and safety impact. A loss of vacuum accident (LOVA) due to a failure of the main vacuum vessel can result in a fast pressurization of the vessel and consequent mobilization dispersion of ...
A. Malizia, I. Lupelli, M. Richetta, M. Gelfusa, C. Bellecci, P. Gaudio, S. K. S. Parashar   +6 more
wiley   +1 more source

Numerical Studies and Simulation of the Lower Hybrid Waves Current Drive by using Fokker – Planck Equation in NSST and HT-7 Tokamaks [PDF]

Journal of Sciences, Islamic Republic of Iran, 2014
Recent experiments on the spherical tokamak have discovered the conditions to create a powerful plasma and ensure easy shaping and amplification of stability, high bootstrap current and confinement energy.
A.A. Molavi Choobini
doaj  

DECAF cross-device characterization of tokamak disruptions indicated by abnormalities in plasma vertical position and current

Nuclear Fusion
Abnormal (deviating from the target) variations in the plasma vertical position Z and current $I_\textrm{p}$ (such as vertical displacements, transient $I_\textrm{p}$ ‘spikes’ and quenches) constitute common elements of a disruption, a phenomenon that is
V. Zamkovska, S.A. Sabbagh, M. Tobin, J.W. Berkery, J.D. Riquezes, Y.S. Park, K. Erickson, J. Butt, J.G. Bak, J. Kim, K.D. Lee, J. Ko, S.W. Yoon, C.J. Ham, L. Kogan, the MAST Upgrade Team   +15 more
doaj   +1 more source

Liquid lithium as divertor material to mitigate severe damage of nearby components during plasma transients. [PDF]

Sci Rep, 2022
Sizyuk V, Hassanein A.
europepmc   +1 more source

First Results of the Implementation of the Doppler Backscattering Diagnostic for the Investigation of the Transition to H-Mode in the Spherical Tokamak Globus-M2. [PDF]

Sensors (Basel), 2023
Ponomarenko A, Yashin A, Kurskiev G, Minaev V, Petrov A, Petrov Y, Sakharov N, Zhiltsov N.   +7 more
europepmc   +1 more source

The Impact of Machine Learning on 2D/3D Registration for Image-Guided Interventions: A Systematic Review and Perspective. [PDF]

Front Robot AI, 2021
Unberath M, Gao C, Hu Y, Judish M, Taylor RH, Armand M, Grupp R.   +6 more
europepmc   +1 more source