Results 41 to 50 of about 4,697,162 (157)

Electron Bernstein Wave Research on NSTX and CDX-U [PDF]

, 2003
Studies of thermally emitted electron Bernstein waves (EBWs) on CDX-U and NSTX, via mode conversion (MC) to electromagnetic radiation, support the use of EBWs to measure the Te profile and provide local electron heating and current drive (CD) in ...
Efthimion, P. C., Taylor, G., Smirnov, A. P., Bigelow, T. S., Wilson, J. R., Jones, B., Rasmussen, D. A., Ram, A. K., Bers, A., Carter, M. D., Harvey, R. W., Bell, G. L., Wilgen, J. B., G. Taylor   +13 more
core   +1 more source

Conceptual design of a divertor Thomson scattering diagnostic for NSTX-U

Review of Scientific Instruments, 2014
A conceptual design for a divertor Thomson scattering (DTS) diagnostic has been developed for the NSTX-U device to operate in parallel with the existing multipoint Thomson scattering system. Higher projected peak heat flux in NSTX-U will necessitate application of advanced magnetics geometries and divertor detachment.
A G, McLean, V A, Soukhanovskii, S L, Allen, T N, Carlstrom, B P, LeBlanc, M, Ono, B C, Stratton   +6 more
openaire   +3 more sources

Studies of lithiumization and boronization of ATJ graphite PFCs in NSTX-U

Nuclear Materials and Energy, 2017
This work examines the effect of boron and lithium conditioned ATJ graphite surface bombarded by low-energy deuterium atoms on the deuterium retention and chemical sputtering.
F.J. Domínguez-Gutiérrez, F. Bedoya, P.S. Krstic, J.P. Allain, A.L. Neff, K. Luitjohan   +5 more
doaj   +1 more source

In search of X-point radiator regime features in NSTX and DIII-D discharges with the snowflake divertor

Nuclear Materials and Energy
Experimental data from NSTX and DIII-D discharges with the snowflake (SF) divertor configurations are analyzed toward the development of the X-point radiator (XPR) concept. The XPR divertor regime was recently realized in standard divertor configurations
V.A. Soukhanovskii, S.L. Allen, M.E. Fenstermacher, C.J. Lasnier, A.G. McLean, F. Scotti, E. Kolemen, A. Diallo, S. Gerhardt, S. Kaye, B.P. LeBlanc, R. Maingi, J.E. Menard, R. Raman, A.W. Hyatt, A.W. Leonard, T.H. Osborne   +16 more
doaj   +1 more source

A plasma–material interaction design basis for NSTX-U flash lithium evaporators

Nuclear Materials and Energy
Plasma–material interaction (PMI) at lithium conditioned plasma facing components (PFCs) depends not only on lithium inventory, but also on coating freshness, chemical state, and spatial coverage.
A. Maan, R. Majeski, C. López Pérez, D.P. Boyle, T. Le, R. Lunsford   +5 more
doaj   +1 more source

Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U

, 2018
The upgrade to the National Spherical Torus eXperiment (NSTX-U) included two main improvements: a larger center-stack, enabling higher toroidal field and longer pulse duration, and the addition of three new tangentially aimed neutral beam sources, which ...
Battaglia, D., Boyer, M., Erickson, K., Mueller, D., Eidietis, N., J. Ferron, Menard, J., D. Mueller, N. Eidietis, Menard, J, Gerhardt, S., Myers, C., Vail, P., Scotti, F, E. Kolemen, D.J. Battaglia, Gerhardt, S, R. Johnson, K. Erickson, Mueller, D, S. Gerhardt, Gates, D., Kolemen, Egemen, Battaglia, DJ, Eidietis, N, M.D. Boyer, Kolemen, E., Boyer, MD, C.E. Myers, Erickson, K, P. Vail, Johnson, R., Scotti, F., Johnson, R, Sabbagh, S., Ferron, J, J. Menard, D.A. Gates, Vail, P, Myers, CE, S.A. Sabbagh, Gates, DA, Sabbagh, SA, Ferron, J., F. Scotti   +44 more
core   +1 more source

Current ramp-up studies for NSTX-U in support of the development of non-inductive current ramp-up scenarios in STs

Nuclear Fusion
The Spherical Tokamak (ST) is a low-aspect-ratio tokamak projected to enable simultaneous operation at high normalized toroidal beta and high bootstrap current fraction. However, a compact ST reactor cannot be built with a full-sized solenoid.
R. Raman, M. Ono, S.C. Jardin, J. Breslau, S.M. Kaye, M. Gorelenkova, T. Rafiq, A. Pankin   +7 more
doaj   +1 more source

Design of the Flowing LIquid Torus (FLIT)

Nuclear Materials and Energy, 2019
The design of the Flowing LIquid Torus (FLIT) at Princeton Plasma Physics Laboratory (PPPL) is presented. FLIT will focus on the development of a liquid metal (LM) diagnostics and divertor system (without a plasma source) suitable for implementation in ...
E. Kolemen, M. Hvasta, R. Majeski, R. Maingi, A. Brooks, T. Kozub   +5 more
doaj   +1 more source

Real-time capable modeling of neutral beam injection on NSTX-U using neural networks

, 2019
A new model of heating, current drive, torque and other effects of neutral beam injection on NSTX-U that uses neural networks has been developed. The model has been trained and tested on the results of the Monte Carlo code NUBEAM for the database of ...
Kaye, S., Erickson, K., Boyer, M.D.
core   +1 more source

Electron Bernstein Wave Research on CDX-U and NSTX [PDF]

, 2001
Mode-converted electron Bernstein waves (EBWs) potentially allow the measurement of local electron temperature (Te) and the implementation of local heating and current drive in spherical torus (ST) devices, which are not directly accessible to low ...
Efthimion, P. C., Taylor, G., Spaleta, J., Munsat, T., Bell, G., Bigelow, T. S., Wilson, J. R., Rasmussen, D., Jones, B., LeBlanc, B. P., Hosea, J. C., Ram, A. K., Bers, A., Forest, C. B., Phillips, C. K., Carter, M. D., Swain, D. W., Harvey, R. W., Kaita, R., Majeski, R., Wilgen, J. B.   +20 more
core   +1 more source