Bulletin of the American Physical Society
62nd Annual Meeting of the APS Division of Plasma Physics
Volume 65, Number 11
Monday–Friday, November 9–13, 2020; Remote; Time Zone: Central Standard Time, USA
Session CP20: Poster Session: Magnetic Confinement: Self-Organized Configurations & Mirrors (2:00pm - 5:00pm)On Demand
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CP20.00001: The Centrifugal Mirror Fusion Experiment (CMFX) Program C. A. Romero-Talamas, I. Abel, B. Beaudoin, A. B. Hassam, T. Koeth A new research program to study the viability of the centrifugal mirror as a thermonuclear fusion confinement scheme is presented. The Centrifugal Mirror Fusion Experiment (CMFX) is being constructed at the University of Maryland to azimuthally rotate a mirror-shaped magnetized plasma to supersonic speeds. The rotation will (a) create a centrifugal force that confines plasma axially; (b) make for a velocity shear that stabilizes instabilities; and (c), at high Mach number, open up a direct pathway to DT fusion energy by exponentially suppressing axial electron heat loss. The proposed work aims for parameters $n=10^{18}/m^3$, $B=0.5~T$, voltage=0.1 MV, radius=0.4 m, plasma length 1.3 m, pulse length 15 ms, and is predicted to achieve $T_e=0.5~keV$, $T_i=0.5~keV$, and a triple product of $10^{17}~ keV-s/m^3$. Deuterium plasmas are expected to produce fusion neutrons at rates of approximately $200/cm^3/s$. The engineering design, planned diagnostics, and experimental plans are discussed. [Preview Abstract] |
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CP20.00002: Transport Considerations for the Centrifugal Mirror Fusion Experiment A. B. Hassam, I. Abel, C. A. Romero-Talamas, B. Beaudoin, T. Koeth In a Centrifugal Mirror, plasma is confined in a simple magnetic mirror configuration. Parallel confinement is attained by parallel centrifugal forces from supersonic azimuthal plasma rotation. The usual mirror loss cone is closed at high sonic Mach numbers, Ms. Rotation is maintained by an externally applied radial voltage, V. Momentum losses are from classical crossfield collisional viscosity and parallel losses strongly mitigated by the large Pastukhov factor, exp[Ms\textasciicircum 2/4]. Turbulent losses are expected to be subdominant due to the large velocity shear. Friction generated from the rotation heats the plasma. Perpendicular heat losses are from classical collisional heat conduction; parallel losses are larger but suppressed strongly by the Pastukhov factor. Fusion conditions can be achieved at Mach numbers of 6 to 7. A zero-dimensional code incorporating the above transport features is used to predict performance for the CMFX. For B$=$0.3T, L$=$1.3m , a$=$0.4m, V$=$80kV, n\textasciitilde 10\textasciicircum 18 /m\textasciicircum 3, we predict \textasciitilde 1keV temperatures. Work supported by the ARPA-E Grant No. DE-AR0001270. [Preview Abstract] |
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CP20.00003: Introducing the Wisconsin HTS Axisymmetric Mirror Jay Anderson, M Clark, C. Forest, B. Geiger, V. Mirnov, S. Oliva, J. Pizzo, O. Schmitz, J. Wallace, G. Kristofek, R. Mumgaard, E. Peterson, A. Ram, D. Whyte, J.` Wright, S. Wukitch, D. Green, R. Harvey, Yu. V. Petrov, B. Srinivisan, A. Hakim Currently in early stage of construction, the Wisconsin HTS Axisymmetric Mirror (WHAM) is motivated by major advances in both technology (high temperature superconductivity) and physics (axisymmetric MHD stability with keV-level electrons). A pair of 17 T mirror coils (from CFS) generates an accessible 4 T contour in the plasma for breakdown and heating with a 110 GHz gyrotron (retired from DIII-D). Endcell biasing shears the rotation profile to impose MHD stability. 25 kV NBI sources a nonthermal ion population; device confinement $\tau_{ii}$ improves rapidly with average ion energy as an ambipolar potential and carefully maintained expander confine electron heat. Early reactor studies rely on MeV-level NBI, we instead pursue a breakthrough approach in which the low energy NBI seed ions are accelerated in situ by HHFW. Numerical support leverages vast expertise from several domestic institutions. [Preview Abstract] |
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CP20.00004: Driven Edge Plasma in Axisymmetric Tandem Mirror Arthur Molvik The cylindrical symmetry of axisymmetric tandem mirrors (once proven MHD stable\footnote{D.D. Ryutov, et al., Phys. Plasmas \textbf{18}, 092301 (2011).}) eliminates neo-classical radial transport, simplifies the engineering of power plants, and could reduce the need for fusion-materials development with rotating $\sim$1 m thick-liquid walls to absorb neutron energy and breed tritium.\footnote{R. W. Moir and R. D. Rognlien, Fusion Sci. and Tech. \textbf{52}, 408 (2007).} It avoids tokamak issues of disruptions and high diverter power density. However, the burning-plasma core must be shielded from gas and vapor from the liquid walls. We propose driving an edge-plasma layer that is thick enough to ionize gas and vapor and carry it to the end walls where it will be pumped. Potential drivers include ion cyclotron, lower hybrid, or low-energy neutral beam injection (NBI) to supplement radial energy transport from the core. Here, we evaluate 0.2 to 20 keV NBI. We discuss the particle and power balance of the edge plasma, possible impacts of radial transport on the required edge-plasma line density Vs central-cell plasma length, equilibration of $T_e$ with $T_i$, and beam divergence, all as a function of deuteron (or DT) beam energy. [Preview Abstract] |
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CP20.00005: Fokker-Planck transport modelling for RF-heated plasmas in open magnetic geometries* Juan F Caneses Marin, Atul Kumar, Louis Wonell, David Green, Cornwall Lau, Donald Batchelor, Richard Goulding Recent interest in radio frequency (RF) heating in plasma devices with open magnetic geometries in both low temperature (\textasciitilde 10 eV) and high temperature (\textasciitilde 1 keV) plasmas has motivated the development and use of 3-dimensional Fokker-Planck solvers : 2 velocity dimensions and 1 dimension in physical space along the magnetic flux. Specific examples of low and high-temperature plasma devices that can benefit from such capability are the MPEX and WHAM devices to be built at ORNL and UW-Wisconsin respectively. We describe recent efforts at ORNL on Fokker-Planck transport modelling for RF-heated plasmas in open geometries using both particle-based methods and continuum approaches. We describe details of the various approaches and present an overview of the latest results. The effect of magnetic field profiles on electron parallel transport is investigated for the upcoming device MPEX. In addition, the process of generating/sustaining sloshing ions in devices such as the WHAM is discussed. Finally, full-wave modelling in warm plasmas is presented to discuss the merits of different heating schemes in such devices and the impact on velocity-space transport. [Preview Abstract] |
Not Participating |
CP20.00006: Compact Torus Plasma Injection Experiments on Keda Torus eXperiment Chen Chen, Sen Zhang, Tao Lan, Ge Zhuang, Defeng Kong, Chijin Xiao, Wandong Liu A new compact torus injection system (KTX-CTI) is developing on Keda Torus eXperiment (KTX) reversed field pinch device. The KTX-CTI is a three-meter long linear device to inject compact torus (CT) plasma into KTX at a high speed. It includes the vacuum vessel, central solenoid, high speed gas valves, timing system, pulse power supplies and CT exclusive diagnostics. Currently, the KTX-CTI is in the engineering commissioning. The maximum injection mass of the CT is 50 $\mu $g for hydrogen, which is about 30{\%} of total KTX plasma particle inventory. The maximum electron density and axial speed are 1x10$^{\mathrm{22}}$m$^{\mathrm{-3}}$ and 150 km/s, respectively. For CTs injected with KTX-CTI having tangential component, it is possible to affect toroidal rotation of the KTX plasma due to the momentum transfered from the CT to KTX bulk plasma. In addition, a small amount of helicity can also be injected for the single helicity mode research expected to improve the confinement for reversed field pinch plasma. As an advanced fueling system with very high penetration speed about two orders higher than common fueling, the KTX-CTI will be used as a prototype device prepared for central fueling of China Fusion Engineering Test Reactor (CFETR) in the future. [Preview Abstract] |
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CP20.00007: Model validation and numerical study of reactor scalability for spheromaks sustained by inductive helicity injection drivers Chris Hansen, Thomas Benedett, Alan Kaptanoglu, Aaron Hossack, Kyle Morgan, Derek Sutherland Numerical investigation of inductive helicity injection drivers, as developed on the HIT-SI family of experiments at the University of Washington, is underway with a focus on developing validated models of relevant driver physics to support exploration and optimization of possible injector configurations for sustainment of spheromak plasmas toward reactor scale. Two extended MHD codes are used: NIMROD (K. Morgan et al., Phys. Plasmas 2017), where the injectors are approximated through boundary conditions on an axisymmetric domain, and PSI-Tet (T. Benedett et al., Phys. Plasmas 2020; A. Kaptanoglu et al., Phys. Plasmas 2020), where the full plasma volume is simulated. Simulations are benchmarked against experimental data from the HIT-SI (two injector), HIT-SI3 (three injector), and HIT-SIU (four injector manifold) devices. Development of a self-consistent external circuit boundary condition in PSI-Tet will be presented. Validated models will be used to explore candidate designs to optimize the effect of toroidal/poloidal mode content, frequency, phasing, and other parameters on resulting sustained spheromak equilibria. [Preview Abstract] |
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CP20.00008: Overview of power and diagnostic upgrades for HIT-SI3 and HIT-SIU experiments A.C. Hossack, K.D. Morgan, C.J. Hansen, D.A. Sutherland The HIT-SI3 device has been upgraded with new switching power amplifiers (SPAs) and capacitors for a 70{\%} increase in nameplate power and a 35{\%} increase in stored energy. The additional power injection enables optimized $j/n$ and longer duration sustainment of high current (\textasciitilde 100 kA) and high current amplification (\textgreater 3) spheromaks. A new, multi-chord, two-color interferometer has been constructed to measure plasma density in the toroidal midplane. The new system is able to operate in HIT-SI3's high density regime (n$_{\mathrm{e}}$ \textgreater 5 x 10$^{\mathrm{19}}$ m$^{\mathrm{-3}})$ where the previous far-infrared interferometer could not. Additionally, an overview of HIT-SI-Upgrade (HIT-SIU), presently under construction, will be given. The three, discrete helicity injectors will be replaced with a manifold which has four connections to the spheromak flux conserver and an RF preionization system will inject plasma into the manifold. The new injector manifold will test lower density startup, improved plasma-facing insulating coatings, applied perturbation spectra predicted to improve performance, and a geometry compatible with larger, future devices. [Preview Abstract] |
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CP20.00009: Tomographic Reconstruction of Plasma Emissivity in HIT-SI3 KuanWei Lee, Aaron Hossack, Christopher Hansen, Derek Sutherland HIT-SI3 is a plasma physics experiment built for studying magnetic confinement of a fusion plasma for eventual clean energy production. HIT-SI3 utilizes steady inductive helicity injection to form and sustain spheromak equilibria. A tomography system has been installed to assess the symmetry of plasma density in HIT-SI3 spheromak plasmas. The tomography diagnostic consists of four toroidal chord fans and three sets of three poloidal fans that provide 3D plasma emission information. Each fan expands from a wide-angle lens with a 130 degree field of view coupled to bundles of fiber optics. The light collected by the fiber optics is split into two paths, filtered at 668 nm and 728 nm He-I emission lines, and imaged by a high-speed camera. The reconstruction of emissivity profiles constitutes a highly underdetermined and ill-posed inversion problem and the basis function method was chosen to find the most physically informed solution. Fifteen basis functions that were used to approximate emissivity profiles were generated by adding radial and angular dependence to the magnetic flux surfaces of the Taylor states. The reconstruction algorithm was tested with synthetic profiles and the algorithm was able to provide accurate reconstructions. The spatial profiles of both He-I emission lines have a hollow shape that is consistent with the results of HIT-SI3 Extended-MHD -simulations. Emissivity profiles of both He-I lines in individual time frames were also reconstructed and the profiles did not vary drastically from frame to frame. [Preview Abstract] |
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CP20.00010: Deformation of Plasma-Facing Surfaces in the ZaP-HD Device Eleanor Forbes, Uri Shumlak Experimental efforts at the University of Washington investigate the use of a sheared-flow-stabilized Z pinch as a platform for a compact fusion reactor. Developing the reactor design will require an understanding of the physical processes occurring at the interface between the plasma and the solid electrode. Recent experiments on the ZaP-HD Flow Z-Pinch Device have investigated the physics of energy transfer from the Z pinch to solid materials and the relationship between bulk plasma parameters and material deformation. Small, cylindrical targets of graphite and boron-nitride are placed on the Z pinch axis and exposed to a series of plasma pulses. Plasma ion temperatures are varied between 0.3 and 1.0 keV and total particle fluence to the targets from 10$^{\mathrm{25}}$ to 10$^{\mathrm{26}}$ m$^{\mathrm{-2}}$. Target surfaces are analyzed with a scanning electron microscope and energy-dispersive x-ray spectroscopy. Stagnated plasma is found to limit the heat flux to the solid surfaces by slowing the diffusion of the magnetic field into the targets. The orientation of the solid surface to the plasma flow affects the surface topography seen in micrographs. These preliminary results provide a foundation for designing an electrode configuration for a higher-power sheared-flow-stabilized Z pinch device. [Preview Abstract] |
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CP20.00011: Observation of a stagnation wave in the Fusion Z-pinch Experiment (FuZE) Elliot Claveau, Uri Shumlak, Brian Nelson, Eleanor Forbes, Aqil Khairi, Anton Stepanov, Tobin Weber, Yue Zhang, Harry McLean The Fusion Z-pinch Experiment (FuZE) is a sheared-flow-stabilized Z pinch based on the ZaP and ZaP-HD experiments. The FuZE device generates neutron-producing, 50-cm-long Z pinches formed from plasma accelerated through coaxial electrodes. The Z-pinches are sustained between a nose cone at the tip of the plasma gun and an end wall at the end of the assembly region flux conserver. The end wall geometry is modified from a central hole to a spoked design and it is found that plasma exhaust through the end wall is dictated by the ratio of magnetic field pressure to the sum of thermal and ram pressures. The limited plasma exhaust results in a reflected wave traveling against the plasma flow. This wave corresponds to a collisional shock transforming flowing background plasma properties to stagnated plasma properties through the Rankine-Hugoniot relations. The plasma linear density is increased across the shock, increasing the pinch current in order to keep the magnetic flux constant. Sheared flow profiles are also changed from hollow to peaked. [Preview Abstract] |
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CP20.00012: Experimental and modeling investigation of longitudinal plasma acceleration on the FuZE experiment. A.D. Stepanov, U. Shumlak, B.A. Nelson, E.L. Claveau, T.R. Weber, Y. Zhang The Fusion Z-Pinch Experiment FuZE investigates sheared-flow stabilization of classic m $=$ 0/1 instabilities in Z-pinches with an embedded axial flow. FuZE consists of a 100 cm coaxial plasma accelerator, where neutral gas is ionized and accelerated in a pulsed electrical discharge, followed by a 50 cm assembly region, where pinches are formed. Maintaining the pinch requires continuous plasma injection provided by a deflagration mode in the coaxial accelerator. Two discharge modes, with and without deflagration, are investigated on FuZE. Pinch formation is observed with deflagration only. Plasma velocities in the assembly region are found to match the ExB velocity estimated in the accelerator based on a 1D circuit model, indicating that a 1D MHD approximation may offer a valid description of the plasma in the accelerator channel. The velocity of magnetic field propagation is found to agree with the snowplow model based on momentum conservation, and the lifetime of the pinch is shown to be in agreement with constraints imposed by mass conservation. [Preview Abstract] |
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CP20.00013: Refinement of neutron measurements for a sheared-flow-stabilized Z pinch A. Khairi, E.L. Claveau, Z.T. Draper, E.G. Forbes, A.D. Stepanov, T.R. Weber, U. Shumlak, H.S. McLean, D.P. Higginson, J.M. Mitrani, B.A. Nelson, Y. Zhang The sheared-flow-stabilized Z pinch is a promising concept for stabilization of the Z-pinch configuration from MHD instabilities, allowing for a longer-lived plasma. The fusion Z-pinch experiment (FuZE) scales this concept to fusion conditions, and has demonstrated sustained neutron production for 5-10 $\mu s$. Operating with pure deuterium and higher charge voltage resulted in an increase in neutron yield, measured by an arrangement of plastic scintillator detectors. Saturation of the detector signal and subsequent shutoff limits the utility of this diagnostic to provide accurate neutron measurements as the experiment scales to higher voltages and yields. To mitigate detector shutoff, neutral density filters were installed between the scintillator and the photo-multiplier tube to reduce light intensity to the photo-multiplier tube. This also allowed investigation of detector pulse pile-up. A composite signal is formed by combining signals from detectors placed at different radial distances, capturing a longer duration of neutron emission and increasing the dynamic range. Monte Carlo N-Particle (MCNP) code is used to replicate the signals from the detector arrays, and to determine their optimal placement. [Preview Abstract] |
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CP20.00014: Scaling of the Sheared-flow-stabilized Z Pinch toward Reactor Conditions BA Nelson, U Shumlak, JR Barhydt, ZT Draper, H Meek, ET Meier, M Quinley, Y Zhang, TR Weber, EL Claveau, EG Forbes, A Khairi, AD Stepanov, HS McLean Zap Energy Inc. (ZEI) is scaling the sheared-flow-stabilized (SFS) Z pinch toward fusion reactor conditions. The UW and LLNL collaborated on the Fusion Z-Pinch Experiment (FuZE) at the UW. FuZE has demonstrated long-duration D-D fusion production periods of 5-10 microseconds [Zhang \textit{et al.}, PRL 2019], thousands of times longer than the 1 ns MHD m$=$0 (sausage) and m$=$1 (kink) instability growth times. FuZE has reached up to 400 kA pinch currents, 1-2 keV ion temperatures, 1-2x10$^{\mathrm{23}}$ m$^{\mathrm{-3}}$ densities, and neutron yields up to $Y_{n}$\textit{ \textasciitilde }10$^{\mathrm{7}}$ neutrons / pulse. An adiabatic model, 2-temperature MHD calculations, and experimental results all indicate a strong dependence of neutron yield with pinch current, $Y_{n}$\textit{ \textasciitilde I}$^{11}$. A new device, FuZE-Q, is being built at ZEI with the goal of reaching equivalent scientific breakeven (scaling D-D operating conditions to ``equivalent'' Q if it were operated instead with D-T) at approximately 600 kA pinch currents. Status, plans, and reactor embodiment designs will be presented. [Preview Abstract] |
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CP20.00015: Development of five-moment two-fluid modeling for Z-pinch physics Eric Meier, Yu. Takagaki, Uri Shumlak The FuZE experiment [Y. Zhang et al., PRL 122 (2019)] has generated pinches with 300-kA current, radii near 1 mm and Ti,e $=$ 1-2 keV. In a reactor, the required current is 1.5 MA, with pinch radius \textless 0.1-mm and Ti,e \textgreater 30 keV. A five-moment two-fluid (5m2f) model is being developed to support experimental progress, aiming to capture the essential Z-pinch physics at modest computational cost. The model is implemented in WARPXM, a DG framework developed at U. Washington. In axisymmetric 5m2f simulations without dissipation, growth of the m$=$0 mode is studied in a scan of a/rLi, where a is the pinch radius, and rLi is the ion Larmor radius. At the extremes of small and large rLi, the simulated growth rates agree with linear MHD and Hall MHD analysis [V. I. Sotnikov et al., PoP 9 (2002)]. At a/rLi \textasciitilde $=$ 2, electron drift speed exceeds the plasma sound speed, and electron drift instabilities appear. At a/rLi $=$ 5.8, corresponding to FuZE conditions, the growth rate peaks at wavenumber kza \textasciitilde $=$ 6, consistent with PIC results [K. Tummel et al., PoP 26 (2019)], and falls with increasing kza. Initial results with a Braginskii-based transport model show damping of growth rates to the PIC-predicted values, supporting the idea that 5m2f modeling will be a valuable tool in future Z-pinch development. [Preview Abstract] |
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CP20.00016: Electron temperature determination in a sheared- flow- stabilized Z-pinch using soft X-rays Yue Zhang, Brian Nelson, Tobin Weber, Uri Shumlak, Luis Delgado-Aparicio, Brentley Stratton The sheared-flow-stabilized Z pinch is a promising concept for economical thermonuclear fusion. The Fusion Z-pinch Experiment (FuZE) has demonstrated sustained neutron production for 5-10 $\mu $s, along with reported plasma parameters of density 10$^{\mathrm{17}}$ cm$^{\mathrm{-3}}$ and ion temperature 1 keV, measured by spectroscopy and force balance. An independent measure of electron temperature is made to further investigate energy confinement in the Z pinch. A compact multi-energy soft X-ray diagnostic has been developed for time, energy and space-resolved measurements of the soft-X-ray emissivity in FuZE Z-pinch plasmas. The diagnostic is simple and robust (no front-end optics). The distinct energy ranges are determined by beryllium foils with different thicknesses. The electron temperature can be obtained by modeling the slope of the continuum radiation from ratios of the available brightness and inverted radial emissivity profiles over multiple energy ranges. The design and setup of the diagnostic, along with obtained experimental data, and analysis results will be presented. [Preview Abstract] |
Not Participating |
CP20.00017: Observing the evolution of self-organized helical states in the Madison Symmetric Torus Patrick VanMeter, Luis Felipe Delgado-Aparicio, Paolo Franz, Brett Chapman, Daniel Den Hartog Magnetically confined plasmas in the Madison Symmetric Torus (MST) reversed-field pinch spontaneously organize into helical equilibria under conditions of at high plasma current and/or low density. This occurs when the inner-most- resonant tearing mode grows to large enough amplitude ($\sim 7\%$ of the equilibrium field strength) that the associated island envelopes the magnetic axis. A suite of x-ray diagnostics, including a new solid-state multi-purpose multi-energy soft- x-ray detector, a hard- x-ray detector, and a two-color diode-based tomographic array are used to study evolution of this quasi-single helicity (QSH) state. Evolution of temperature and impurity density profiles are inferred using an integrated data analysis procedure. Residual tearing mode activity is observed to resume during the quasi-stationary period and is correlated with intermittency in the thermal confinement. These observations are compared with the predictions of a predator-prey model by Terry, \emph{et al.} which proposes that strong magnetic or flow shear suppresses energy transfer between tearing modes, significantly extending the lifetime of the QSH state. Work supported by US Department of Energy. [Preview Abstract] |
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CP20.00018: The Lundquist number scaling of nonlinear MHD fluctuations in MST RFP plasmas S.Z. Kubala, D.J. Den Hartog, K.J. McCollam, J.S. Sarff, P.D. Van Meter Nonlinear MHD fluctuations appear in both natural and magnetic confinement settings, such as the solar wind, self-organization dynamics in the RFP and spheromak, and current disruptions in tokamak plasmas. Here we describe parameter scaling experiments aimed at understanding the underlying nonlinear MHD dynamics in RFP plasmas. Data have been gathered spanning a wide range of parameter space characterized by Lundquist number, $S \sim 10^4 - 10^7$, and density, $\bar{n_e}/n_G$, where $n_G$ is the empirical density limit. A new programmable power supply allows low-current operation at low $S$, which overlaps with parameters available in numerical modeling. Quantitative comparisons are made with results from the nonlinear MHD codes DEBS and NIMROD. A transition from quasi-continuous sustainment to discrete sawtoothing events is observed going from low to high $S$. The spectral properties of the magnetic fluctuations reveal the transition to sawtoothing. The threshold between the two regimes is around $S \sim 10^5$. Work supported by U.S. DoE. [Preview Abstract] |
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CP20.00019: Modeling RFPs from self-consistent steady states of a cylindrical pinch Urvashi Gupta, Carl Sovinec Most computational modeling of RFP dynamics has focused on resistive diffusion without pressure evolution under the assumption that any pressure-driven effects are small. RFPs, however have bad curvature. Thus, even when $\Delta $' is negative, pressure-gradients can drive both resistive tearing and interchange (Coppi et al, NF 1966). For self-consistent modeling with pressure evolution from an equilibrium pressure gradient, we initialize our model from steady state solutions of the complete set of resistive-MHD equations for a cylindrical pinch with a strong guide field. With no shear in the equilibrium, these 1D profiles form symmetric Ohmic steady states that are in classical particle-transport balance. Two approaches have been adopted for the steady state temperature equation - the first model has a uniform background temperature with no Ohmic source while the second includes an equilibrium temperature gradient with thermal conduction balancing Ohmic heating. 3D non-linear evolution from both these profiles is initially violently unstable to interchange. They develop shear and undergo current-gradient relaxation leading to a final saturated state that is tearing dominant like an RFP. Comparison of time-dependent results from the two profiles is expected to provide information on thermal effects in RFP relaxation. [Preview Abstract] |
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