NSTX-U research advancing the physics of spherical tokamaks
Authors:
Top Cited Papers
Open Access
- 15 August 2024
- journal article
- research article
- Published by IOP Publishing in Nuclear Fusion
- Vol. 64 (11) , 112004
Abstract
The objectives of NSTX-U research are to reinforce the advantages of STs while addressing the challenges. To extend confinement physics of low-A, high beta plasmas to lower collisionality levels, understanding of the transport mechanisms that set confinement performance and pedestal profiles is being advanced through gyrokinetic simulations, reduced model development, and comparison to NSTX experiment, as well as improved simulation of RF heating. To develop stable non-inductive scenarios needed for steady-state operation, various performance-limiting modes of instability were studied, including MHD, tearing modes, and energetic particle instabilities. Predictive tools were developed, covering disruptions, runaway electrons, equilibrium reconstruction, and control tools. To develop power and particle handling techniques to optimize plasma exhaust in high performance scenarios, innovative lithium-based solutions are being developed to handle the very high heat flux levels that the increased heating power and compact geometry of NSTX-U will produce, and will be seen in future STs. Predictive capabilities accounting for plasma phenomena, like edge harmonic oscillations, ELMs, and blobs, are being tested and improved. In these ways, NSTX-U researchers are advancing the physics understanding of ST plasmas to maximize the benefit that will be gained from further NSTX-U experiments and to increase confidence in projections to future devices.Keywords
Funding Information
- Fusion Energy Sciences (DE-AC02-05CH11231)
- Culham Centre for Fusion Energy (EP/R034737/1)
This publication has 127 references indexed in Scilit:
- Theory of plasma blob formation and its numerical and experimental validationsReviews of Modern Plasma Physics, 2023
- Model-based linear–quadratic–integral controller for simultaneous regulation of the current profile and normalized beta in NSTX-UFusion Engineering and Design, 2023
- Fast model-based scenario optimization in NSTX-U enabled by analytic gradient computationFusion Engineering and Design, 2023
- Hybrid simulation of energetic particles interacting with magnetohydrodynamics using a slow manifold algorithm and GPU accelerationComputer Physics Communications, 2022
- Closed-loop simulation with Grad-Shafranov equilibrium evolution for plasma control system developmentFusion Engineering and Design, 2019
- Li collection experiments on T-11M and T-10 in framework of Li closed loop conceptFusion Engineering and Design, 2012
- Finalizing the ITER divertor design: The key role of SOLPS modelingFusion Engineering and Design, 2011
- Lithium coatings on NSTX plasma facing components and its effects on boundary control, core plasma performance, and operationFusion Engineering and Design, 2010
- VORPAL: a versatile plasma simulation codeJournal of Computational Physics, 2004
- Neutral Gas Transport Modeling with DEGAS 2Contributions to Plasma Physics, 1994