Results 41 to 50 of about 670 (162)

Validating the simulation of beam-ion charge exchange in MAST Upgrade [PDF]

, 2023
Simulation of the impact of charge-exchange (CX) reactions on beam ions in the Mega Amp Spherical Tokamak (MAST) Upgrade was compared to measurements carried out with a fission chamber (neutron fluxes) and a fast ion deuterium-alpha (FIDA) diagnostic.
, MAST-U team, Allan, Scott, Harrison, James R., Jackson, Andrew R., Kurki-Suonio, Taina, McClements, Kenneth G., Michael, Clive A., Moulton, David, Ollus, Patrik, Patel, Bhavin S., Robson, Michael, Snicker, Antti, Varje, Jari, Vincent, Charles   +13 more
core   +2 more sources

Multi-machine analysis of termination scenarios with comparison to simulations of controlled shutdown of ITER discharges [PDF]

, 2018
To improve our understanding of the dynamics and control of ITER terminations, a study has been carried out on data from existing tokamaks. The aim of this joint analysis is to compare the assumptions for ITER terminations with the present experience ...
Bae, Y.S., de Vries, P.C., García Muñoz, Manuel, Gerhardt, S., Gong, X., Jet Contributors, Luce, T.C.   +6 more
core   +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

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

Nonlinear simulations of GAEs in NSTX-U

Physics of Plasmas
A set of nonlinear simulations has been performed in order to study the nonlinear evolution of unstable global Alfvén eigenmodes in the National Spherical Torus Experiment-Upgrade (NSTX-U). Results of the single toroidal mode number, n, simulations are compared with a full nonlinear simulation (all toroidal harmonics included). In single-n simulations,
E. V. Belova, E. D. Fredrickson, N. A. Crocker   +2 more
openaire   +1 more source

Addressing the challenges of plasma-surface interactions in NSTX-U

2014 IEEE 41st International Conference on Plasma Sciences (ICOPS) held with 2014 IEEE International Conference on High-Power Particle Beams (BEAMS), 2014
The importance of conditioning plasma-facing components (PFCs) has long been recognized as a critical element in obtaining high-performance plasmas in magnetic confinement devices. Lithium coatings, for example, have been used for decades for conditioning PFCs.
R. Kaita, T. Abrams, M. Jaworski, M. Lucia, J. Nichols, C. H. Skinner, D. Stotler, J-P. Alain, F. Bedoya   +8 more
openaire   +2 more sources

3D ion gyro-orbit heat load predictions for NSTX-U

Nuclear Fusion, 2022
Abstract High power tokamaks operate with divertor heat loads capable of destroying the plasma facing components (PFCs). High fidelity heat load predictions are necessary to ascertain the PFC state for design and during operation. Typical heat flux calculations are 2D, time invariant, and assume that power flows directly along the ...
T. Looby, M.L. Reinke, A. Wingen, T. Gray, E.A. Unterberg, D. Donovan   +5 more
openaire   +1 more source

Overview of NSTX Upgrade initial results and modelling highlights [PDF]

, 2017
The National Spherical Torus Experiment (NSTX) has undergone a major upgrade, and the NSTX Upgrade (NSTX-U) Project was completed in the summer of 2015. NSTX-U first plasma was subsequently achieved, diagnostic and control systems have been commissioned,
Allain, J. P., Battaglia, D. J., Bedoya, F., Bell, R. E., Belova, E., Berkery, J. W., Boyer, M. D., Crocker, N., Diallo, A., Ebrahimi, F., Ferraro, N., Fredrickson, E., Frerichs, H., Gerhardt, S., Gorelenkov, N., Guttenfelder, W., Heidbrink, W., Kaita, R., Kaye, S. M., Kriete, D. M., Kubota, S., LeBlanc, B. P., Liu, D., Meier, E., Menard, J. E.   +24 more
core   +1 more source

Generation Of High Non-inductive Plasma Current Fraction H-mode Discharges By High-harmonic Last Wave Heating In The National Spherical Torus Experiment [PDF]

, 2012
1.4 MW of 30 MHz high-harmonic fast wave (HHFW) heating, with current drive antenna phasing, has generated a Ip = 300kA, BT (0) = 0.55T deuterium H-mode plasma in the National Spherical Torus Experiment that has a non-inductive plasma current fraction ...
Bonoli, P. T., Kessel, C. E., LeBlanc, B. P., Mueller, D., Phillips, D. K., Ryan, P. M., Taylor, G., Valeo, E. J., Wilson, J. R., Wright, J. C.   +9 more
core   +1 more source

Two-dimensional AXUV-based radiated power density diagnostics on NSTX-U [PDF]

Review of Scientific Instruments, 2014
A new set of radiated-power-density diagnostics for the National Spherical Torus Experiment Upgrade (NSTX-U) tokamak have been designed to measure the two-dimensional poloidal structure of the total photon emissivity profile in order to perform power balance, impurity transport, and magnetohydrodynamic studies. Multiple AXUV-diode based pinhole cameras
Delgado-Aparicio, L., Bell, R. E., Tritz, K., Diallo, A., Gerhardt, S. P., LeBlanc, B., Kozub, T. A., Faust, Ian Charles, Stratton, B. C., Parker, R.   +9 more
openaire   +3 more sources