Since 18 of December 2019 uses Nucleus credentials. Visit our help pages for information on how to Register and Sign-in using Nucleus.

May 10 – 15, 2021
Virtual Event
Europe/Vienna timezone
The Conference will be held virtually from 10-15 May 2021

[OV POSTER TWIN] Recent NSTX-U Theory, Modeling and Analysis Results

May 10, 2021, 2:00 PM
4h 55m
Virtual Event

Virtual Event

Overview Poster Overview OV-OV/P Overview Posters


Walter Guttenfelder (Princeton Plasma Physics Laboratory)


The mission of the spherical tokamak NSTX-U is to advance the physics basis and technical solutions required for optimizing the configuration of next-step tokamak fusion devices, and to advance the development of the ST concept towards a compact, low-cost Pilot Plant 1. NSTX-U will operate at up to 2 MA and 1 T with up to 10 MW of Neutral Beam Injection (NBI) power for 5 seconds and 4 MW of High Harmonic Fast Wave (HHFW) power. NSTX-U has three main objectives: to explore confinement and stability at low aspect ratio and high beta at low collisionality, to develop the physics understanding and control tools to ramp-up and sustain high performance plasmas in a fully-non-inductive regime, and to develop and evaluate conventional and innovative power and particle handling techniques to optimize plasma exhaust in high performance scenarios. Following the initial 2016 NSTX-U run campaign, analysis has continued during NSTX-U Recovery to address physics issues to develop understanding and capabilities that, once operation commences, will aid in achieving these three objectives.

Stability and 3D physics: The resistive DCON model for calculating tearing mode stability ($\Delta'$) has been developed, benchmarked against extended-MHD (M3D-C1) simulations, and used to identify regions in $q_{95}-\beta_N$ that are simultaneously stable to both 2/1 tearing modes (Fig.1) and n=1 ideal kink. 2/1 tearing stability ($\Delta'<0$, stable) as a function of $q_{95}$ and $\beta_N$ for a 2 MA, 1 T, 12 MW NSTX-U scenario. M3D-C1 has been extended to predict Te and Ti independently in the presence of impurities during a thermal quench 2. The simulations show a contraction of the current channel that is sensitive to temperature, and a fast stochastization of the B-field, highlighting the difficulty in cooling the plasma while avoiding a thermal quench using impurity injection. Continued analysis on 3D error fields have shown that misalignment of the toroidal field (TF) was the largest source of the error field on NSTX-U during initial operation in 2016, and these calculations, guided by constraints on the field line pitch at the divertor plates in order to mitigate potentially high heat fluxes, were used to drive the engineering tolerances for TF shift and tilt for NSTX-U Recovery [3]. Additional calculations show that misalignments in other PF coils lead to extended divertor footprints but which are contained within the divertor region designed to handle high heat fluxes [4].

Energetic particle (EP) physics: The phase-space-resolved reduced EP transport kick model has been extended to include non-Alfvénic low-frequency perturbations, reproducing observations of (i) large fast ion losses due to synergistic effects when TAE and fishbones/kink instabilities occur simultaneously, and (ii) enhanced fast ion loss due to NTMs when the island width exceeds a threshold [5]. The stability and scaling of global Alfven eigenmodes (GAEs), previously correlated with central Te flattening in NSTX, has been predicted using hybrid MHD/kinetic-fast-ion simulations [6] and also newly derived analytic instability conditions [7], revealing a previously unidentified instability regime necessary to explain observed GAE excitation and stabilization. The chirping and avalanche behavior of Alfven eigemodes that can influence fast-ion losses in NSTX-U (and burning plasma $\alpha$ losses) has been predicted using a guiding center code with a delta-f formalism [8]. New analysis from NSTX and NSTX-U data has provided a detailed picture of ion cyclotron emission (ICE), being considered as a possible diagnostic of confined $\alpha$’s in burning plasma experiments [9]. A self-consistent resonance-broadened quasi-linear (QL) model has been developed for relaxation of fast ion distribution function by Alfvenic modes [10].

Transport physics: Analysis in moderate $\beta$ NSTX scenarios using gyrokinetic simulations coupled with a novel “synthetic diagnostic” identify conditions where both electron thermal transport and turbulence measured by high-k microwave scattering are explained entirely by short-wavelength electron-scale ETG turbulence [11]. Gyrokinetic analysis in high-$\beta_{pol}$ scenarios envisioned for high non-inductive fraction operation indicates the deep-core profiles (with relatively flat Te) sit very near KBM (or EPM) limits when including only thermal ions (or thermal + fast ion species), suggesting core profiles may ultimately be constrained by $\nabla p$-limited ballooning modes. Analysis of enhanced Pedestal (EP) H-modes demonstrates that this high confinement (H98$\leq$1.8), wide-pedestal ($\Delta\psi_{N,ped}\leq0.4$), ELM-free regime is accessed at low edge ion collisionality, e.g. via reduced wall recycling with lithium wall coatings. While MTM, TEM and ETG instabilities predicted in this region may account for electron thermal losses, it is hypothesized that peeling-ballooning and near-marginal KBM instabilities (predicted via MHD and gyrokinetic simulations, respectively, Fig. 2) may enhance edge particle transport during the evolution to the EPH phase that helps to sustain the low-density, low-collisionality state. (a) Eigenfunctions of unstable ideal MHD modes for multiple toroidal harmonics. (b) Experimental MHD-$\alpha$ (lines) and gyrokinetic KBM thresholds (symbols) for both H and EPH mode.

RF physics: A new 2D full wave code (FW2D) has been updated to predict the sensitivity of SOL losses to variations in the realistic boundary shape for high harmonic fast wave (HHFW) heating [12]. Losses are further predicted to be minimized when the SOL density is near the critical density for fast wave cutoff, as found in experiments. Calculations of HHFW deposition in the presence of NBI using AORSA identify a competition between electron and fast ions absorption [13]. Additional simulations show that a sufficient concentration of H+ minority species could open up new HHFW heating scenarios in NSTX-U without NBI.

Scenarios & Control: A unified, physics-based reduced model for direct inductive startup, which computes the timing of plasma initiation and duration needed for plasma density buildup, has been developed for both NSTX-U and MAST-U [14]. Physics-based control-oriented models have been used to develop advanced-control approaches to determine neutral-beam current-drive requirements and evolutions to track prescribed current profiles in closed-loop [15], as well as to iteratively optimize the access to high-performance scenarios [16]. Aided by this is the development of a neural network-based description of beam heating and current drive profiles, well suited for rapid calculations and real-time application [17]. Development of a physics-based algorithm for closed loop feedback control of snowflake divertor configurations will provide real-time tracking and control capabilities [18].

The NSTX-U Recovery planning is ongoing, with NSTX-U targeting resumption of operations in 2021 [19].

This work was supported by US Department of Energy Contract No. DE-AC02- 09CH11466.

1 Menard, J.E., et al., this conference.
2 Ferraro, N.M., et al., Nucl. Fusion 59 016001 (2019).
[3] Ferraro, N.M., et al., Nucl. Fusion 59 086021 (2019).
[4] Munaretto, S., et al., Nucl. Fusion 59 076039 (2019).
[5] Podesta, M, et al., this conference.
[6] Belova, E., et al., this conference.
[7] J. B. Lestz et al., Physics of Plasmas 27, 022512 & 022513 (2020);
[8] White, R., et al., this conference.
[9] Fredrickson, E., et al., this conference.
[10] Gorelenkov, et al., this conference.
[11] Ruiz Ruiz, J., et al., Plasma Phys. Cont. Fusion 61 115015 (2019)
[12] Kim, E.-H., et al., Phys. Plasmas 26 062501 (2019)
[13] Bertelli, N., et al., Nucl. Fusion 59 086006 (2019)
[14] Battaglia, D.J., et al., Nucl. Fusion 59 126016 (2019)
[15] Ilhan, Z.O., et al., Fusion Eng. and Design 146 555 (2019)
[16] Wehner, W.P., et al., Fusion Eng. and Design 146 547 (2019)
[17] Boyer, M.D., et al., this conference.
[18] Vail, P.J., et al., Plasma Phys. Cont. Fusion 61 035005 (2019)
[19] Gerhardt, S.P., et al., this conference.

Affiliation Princeton Plasma Physics Laboratory
Country or International Organization United States

Primary authors

Presentation materials

There are no materials yet.