Results 61 to 70 of about 4,697,162 (157)

Experimental scaling of compressional Alfvén eigenmode stability

Nuclear Fusion
Both co-propagating and counter-propagating compressional Alfvén eigenmodes (CAE) are relatively ubiquitous in NSTX plasmas with toroidal field strengths of ⩽4.65 kG, but are largely absent in the NSTX-U plasmas with toroidal fields of 5.7–5.9 kG.
E.D. Fredrickson
doaj   +1 more source

Optimization of lithium vapor box divertor evaporator location on NSTX-U using SOLPS-ITER

Nuclear Fusion
Commercial fusion reactors will be faced with extremely high divertor target heat fluxes that will require mitigation. Simulations of detachment in an NSTX-U scenario projected to have 92 MW m ^−2 unmitigated peak target heat flux are presented, which ...
E.D. Emdee, R.J. Goldston, A. Khodak, R. Maingi   +3 more
doaj   +1 more source

Overview of the Systems Engineering Process as it Applies to NSTX-U

Fusion Science and Technology, 2019
AbstractThis paper addresses the systems engineering (SE) processes used for the National Spherical Torus Experiment-Upgrade (NSTX-U).
openaire   +2 more sources

Overview of Innovative PMI Research on NSTX-U and Associated PMI Facilities at PPPL

, 2012
Developing a reactor compatible divertor and managing the associated plasma material interaction (PMI) has been identified as a high priority research area for magnetic confinement fusion.
Jaworski, M., Maingi, R., Ono, M., Skinner, C. N., National Spherical Torus Experiment (Project), Kaita, R., Allain, J. P., Scotti, F., Soukhanovskii, V. A.   +8 more
core   +1 more source

Variations in lithium vapor cave performance predictions due to radial transport and recycling assumptions

Nuclear Fusion
The lithium vapor cave is a detached divertor design that uses a single private flux region baffle to contain a dense cloud of lithium vapor to dissipate heat flux.
E.D. Emdee, R.J. Goldston, M.S. Parsons, M. Porcelli   +3 more
doaj   +1 more source

Heat Flux Model Validation Utilizing Convolutional Neural Networks and Sub-surface Thermocouples for NSTX-U [PDF]

, 2018
A proof of concept convolutional neural network (CNN) has been developed to assist in operating tokamaks outside of existing empirical scalings for the heat flux width, λq [lambda-q].
Looby, Thomas Patrick
core  

Modeling of divertor heat flux limits and lithium vapor shielding in NSTX-U using UEDGE code

Nuclear Fusion
Managing extreme heat and particle fluxes to divertor targets remains a critical challenge for high-power spherical tokamaks such as NSTX-U. In this work, UEDGE simulations coupled self-consistently with a two-dimensional wall transport solver (Wall-Li ...
M.S. Islam, M.V. Umansky, V.A. Soukhanovskii   +2 more
doaj   +1 more source

Regarding the optimization of O1-mode ECRH and the feasibility of EBW startup on NSTX-U

, 2018
Recently published scenarios for fully non-inductive startup and operation on the National Spherical Torus eXperiment Upgrade (NSTX-U) (Menard et al 2012 Nucl. Fusion 52 083015) show Electron Cyclotron Resonance Heating (ECRH) as an important component
N A Lopez, Poli, F, Lopez, N, F M Poli
core   +1 more source

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

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