Results 21 to 30 of about 1,608 (195)

NSTX Diagnostics for Fusion Plasma Science Studies [PDF]

, 2001
This paper will discuss how plasma science issues are addressed by the diagnostics for the National Spherical Torus Experiment (NSTX), the newest large-scale machine in the magnetic confinement fusion (MCF) program.
Paoletti, F., Stutman, D., Team, and the NSTX, Bitter, M., Kaita, R., Roquemore, L., Johnson, D., Levinton, F.   +7 more
core   +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

“Snowflake” divertor configuration in NSTX [PDF]

Journal of Nuclear Materials, 2011
Abstract Steady-state handling of divertor heat flux is a critical issue for present and future conventional and spherical tokamaks with compact high power density divertors. A novel “snowflake” divertor (SFD) configuration that takes advantage of magnetic properties of a second-order poloidal null has been predicted to have a larger plasma-wetted ...
Soukhanovskii, V. A., Ahn, J. W., Bell, R. E., Gates, D. A., Gerhardt, S., Kaita, R., Kolemen, E., Kugel, H. W., LeBlanc, B. P., Maingi, R., Maqueda, R., McLean, A., Menard, J. E., Mueller, D. M., Paul, S. F., Raman, R., Roquemore, A. L., Ryutov, D. D., Scott, H. A.   +18 more
openaire   +1 more source

Blob wakes in NSTX

Physics of Plasmas, 2019
Transient small-scale structures were identified in the wake of blobs moving poloidally through the scrape-off layer of high-powered H-mode plasmas in NSTX, using the gas puff imaging (GPI) diagnostic. These blob wakes had a poloidal wavelength in the range of λpol = 3.5 ± 0.7 cm, which is significantly smaller than the average blob scale of Lpol ∼ 12 ...
S. J. Zweben, J. R. Myra, A. Diallo, D. A. Russell, F. Scotti, D. P. Stotler   +5 more
openaire   +2 more sources

A megawatt-level 28 GHz heating system for the National Spherical Torus Experiment Upgrade

EPJ Web of Conferences, 2015
The National Spherical Torus Experiment Upgrade (NSTX-U) will operate at axial toroidal fields of ≤ 1 T and plasma currents, Ip ≤ 2 MA. The development of non-inductive (NI) plasmas is a major long-term research goal for NSTX-U.
Taylor G., Ellis R.A., Fredd E., Gerhardt S. P., Greenough N., Harvey R. W., Hosea J. C., Parker R., Poli F., Raman R., Shiraiwa S., Smirnov A. P., Terry D., Wallace G., Wukitch S.   +14 more
doaj   +1 more source

Elemental and topographical imaging of microscopic variations in deposition on NSTX-U and DIII-D samples

Nuclear Materials and Energy, 2019
Tokamak plasma facing components have surface roughness that can cause microscopic spatial variations in erosion and deposition and hence influence material migration, erosion lifetime, dust and tritium accumulation, and plasma contamination.
C.H. Skinner, C.P. Chrobak, M.A. Jaworski, R. Kaita, B.E. Koel   +4 more
doaj   +1 more source

Emission in the ion cyclotron range of frequencies (ICE) on NSTX and NSTX-U

Physics of Plasmas, 2019
We report here on observations of magnetic fluctuations in the ion-cyclotron frequency range on NSTX and NSTX-U. In many respects, the fluctuations appear similar to the ion cyclotron emission (ICE) seen in conventional tokamaks. However, a significant difference between previous observations of ICE and the ICE on NSTX is that the frequency of ICE in ...
E. D. Fredrickson, N. N. Gorelenkov, R. E. Bell, A. Diallo, B. P. LeBlanc, M. Podestà   +5 more
openaire   +2 more sources

Results of NSTX heating experiments [PDF]

IEEE Transactions on Plasma Science, 2003
The National Spherical Torus Experiment (NSTX) at Princeton University, Princeton, NJ, is designed to assess the potential of the low-aspect-ratio spherical torus concept for magnetic plasma confinement. The plasma has been heated by up to 7 MW of neutral beam injection (NBI) at an injection energy of 100 keV and up to 6 MW of high harmonic fast wave ...
D. Mueller, M. Ono, M.G. Bell, R.E. Bell, M. Bitter, C. Bourdelle, D.S. Darrow, P.C. Efthimion, E.D. Fredrickson, D.A. Gates, R.J. Goldston, L.R. Grisham, R.J. Hawryluk, K.W. Hill, J.C. Hosea, S.C. Jardin, H. Ji, S.M. Kaye, R. Kaita, H.W. Kugel, D.W. Johnson, B.P. LeBlanc, R. Majeski, E. Mazzucato, S.S. Medley, J.E. Menard, H.K. Park, S.F. Paul, C.K. Phillips, M.H. Redi, A.L. Rosenberg, C.H. Skinner, V.A. Soukhanovskii, B. Stratton, E.J. Synakowski, G. Taylor, J.R. Wilson, S.J. Zweben, W.D. Dorland, Y.K.M. Peng, R. Barry, T. Bigelow, C.E. Bush, M. Carter, R. Maingi, M. Menon, P.M. Ryan, D.W. Swain, J. Wilgen, S.A. Sabbagh, F. Paoletti, J. Bialek, W. Zhu, R. Raman, T.R. Jarboe, B.A. Nelson, R.J. Maqueda, G.A. Wurden, R.I. Pinsker, M. Schaffer, J. Ferron, L. Lao, D. Stutman, M. Finkenthal, W. Wampler, S. Kubota, W.A. Peebles, M. Gilmore, T.K. Mau, K.C. Lee, C.W. Domier, B.H. Deng, M. Johnson, N.C. Luhmann, P. Bonoli, A. Bers, A. Ram, R. Akers, Y. Takase, A. Ejiri, Y. Ono, S. Shiraiwa, N. Nishino, O. Mitarai, M. Nagata, J.G. Yang, H. Na, D. Pacella   +87 more
openaire   +1 more source

Images of edge turbulence in NSTX [PDF]

IEEE Transactions on Plasma Science, 2005
The two-dimensional structure of edge plasma turbulence has been measured in the National Spherical Torus Experiment (NSTX) by viewing the emission of the D/sub a/ spectral line of deuterium. Images have been made at framing rates of up to 250 000 frames/s using an ultra-high speed charged coupled device camera developed by Princeton Scientific ...
S.J. Zweben, C.E. Bush, R.J. Maqueda, T. Munsat, D.P. Stotler, J.L. Lowrance, V.J. Mastrocola, G. Renda   +7 more
openaire   +1 more source

Optimization of the snowflake divertor for power and particle exhaust on NSTX–U

Nuclear Materials and Energy, 2019
In this paper, simple analytical modeling and numerical simulations performed with the multi-fluid edge transport code UEDGE are used to identify optimal snowflake divertor (SFD) configurations for heat flux mitigation and sufficient cryopumping ...
P.J. Vail, O. Izacard, E. Kolemen
doaj   +1 more source