Recent Publications

Yesterday

Plasma Physics and Controlled Fusion

Synthetic diagnostics and integrated modeling: Bridging the gap between measurement and interpretation in magnetic confinement fusion

Anna Glasser

Plasma Physics and Controlled FusionyesterdayPlasma & ConfinementControl & DiagnosticsAI, Modeling & Simulation

In magnetic confinement fusion, we rarely measure physical quantities directly; instead, we measure their indirect signatures - photons, currents, and phase shifts. Bridging the gap between these raw signals and the physical parameters of interest (such as density or temperature) has traditionally relied on the inverse problem, a mathematical reconstruction process often plagued by ambiguity and ill-posedness. This tutorial advocates for a paradigm shift toward forward modeling via Synthetic Diagnostics. By processing simulation data through the same transfer functions as experimental instruments, we can translate theoretical predictions into synthetic signals, enabling a rigorous comparison with experiment. We formalize this approach within the TWINTOK framework, a Digital Twin architecture designed for systematic validation. Through detailed case studies - ranging from the spectroscopic evaluation of divertor detachment to the full-wave modeling of turbulence staircases - we demonstrate how synthetic diagnostics reveal physics that standard inversions often miss, such as the significant contribution of wall reflections to bolometric signals. As the community moves toward ITER and fusion power plants, where diagnostic access will be limited and interpretation challenging, this forward modeling approach provides the essential link to validate our predictive capabilities.

Nuclear Fusion

System identification simulations using the Advanced Fluid Neutral model and Wide Grid formalism in SOLPS-ITER.

Stijn Peter Kobussen, Sander Van den Kerkhof, Federico Cursi, Wouter de Keyser, Gijs Lukas Derks, Bob Kool, David Moulton, Kevin Verhaegh, M van Berkel, Sven Wiesen

This work presents a first step towards using the SOLPS-ITER code package for synthetic system identification using multisine perturbations. Numerical modelling is used to replicate system identification experiments performed to establish exhaust control done on MAST-U. These experiments involve perturbing the gas injection rate and observing the SOL response in the frequency domain. The model used is the Advanced Fluid Neutral (AFN) model of SOLPS-ITER, implemented in the Wide Grids (WG) version of the code. The grid was generated with the Grid Optimization and Adaptation Toolbox (GOAT) and extends to the vessel wall, to enable calculating fluid neutral parameters across the entire domain. New boundary condition types were implemented in the code to allow for multisine gas injection perturbations, as well as reservoir models for remote vessel regions without plasma. In steady state, it is possible to simulate plasmas ranging from attached to deeply detached using different gas injection rates. This allows for comparison between simulation and experimental results at similar levels of detachment. Comparison between simulation and experimental data in the frequency domain shows that the AFN SOLPS-ITER simulations predict faster response times to divertor fuelling perturbations than the experiments, likely in part due to the fluid approximation used for the neutrals. When including the reservoir models for remote vessel regions the phase shifts increase, but are still too low compared to experiments.

Physics of Plasmas

Drift-kinetic PIC model for simulations of longitudinal plasma confinement in mirror traps

V. V. Glinskiy, I. V. Timofeev, V. V. Prikhodko

The paper presents a 1D2V electrostatic particle-in-cell (PIC) model with a drift-kinetic description of all particle types, aiming to simulate classical longitudinal plasma transport in axially symmetric open traps. The model generalizes the semi-implicit PIC method with exact conservation of energy and charge to the case of collisional plasma and adapts it to boundary conditions on perfectly conducting walls with a floating potential. The implementation of Coulomb collisions is tested on the problem of temperature relaxation in a two-component plasma and demonstrates good agreement with the analytical theory. Since the quasi-neutral approximation is not assumed and Ampère's law is used to find the electric field, the model is able to correctly reproduce the ambipolar electric potential profile up to the walls. At the same time, the main advantage of implicit PIC simulations—the ability to use large grid steps, many times larger than the Debye radius—does not prevent the key elements of the Debye sheath physics from being reproduced correctly. In particular, the magnitude of the near-wall drop in electric potential as well as the Bohm criterion are found to be independent of whether the Debye scale is resolved or not. A comparison of stationary plasma profiles formed in a mirror trap in the presence of a constant particle source with similar profiles from the hybrid (fluid electrons) code MIDAS showed that the electron temperature, potential, and density of the confined plasma may differ by a noticeable amount, up to 15%–20%.

Journal of Plasma Physics

Two-fluid boundary turbulence simulations in reversed field pinch plasmas

M. Giacomin, B. Momo, I. Predebon, N. Vianello, M. Zuin

Journal of Plasma PhysicsyesterdayPlasma & ConfinementAI, Modeling & Simulation

Turbulent transport in magnetic confinement fusion devices governs the overall plasma confinement properties and regulates the plasma-material interaction at the first wall. In the plasma boundary, turbulence is typically investigated through three-dimensional two-fluid flux-driven turbulence simulations. In this work, the GBS boundary turbulence code is extended to enable turbulence simulations in reversed field pinch configurations, encompassing the reversal surface and an arbitrary level of magnetic chaos. The differential operators implemented in the code are modified to avoid the approximations of large-aspect ratio and weak poloidal magnetic field. Three-dimensional Poisson and Ampere solvers are implemented to allow for turbulence simulations in conditions of partially or fully disrupted magnetic flux surfaces. This modified version of the GBS code is then applied to simulate turbulence in the boundary of RFX-mod reversed field pinch plasmas. Turbulent eddies across the reversal surface show properties similar to those typically found in tokamak boundary turbulence simulations. Despite the good agreement found with experimental measurements, these simulations reveal a significant limitation of the fluid-based turbulence modeling of the edge region in reversed field pinch plasmas, which arises from the intrinsically short parallel connection length. This conclusion is also supported by a linear gyrokinetic analysis that identifies trapped electron modes as the dominant microinstability in this region.

Oct 8

Plasma Physics and Controlled Fusion

Stellarator island divertor shape optimization for reduced peak heat fluxes

Avigdor Veksler, Aaron Bader, Heinke Frerichs, Elizabeth Joy Paul

An automated algorithm to construct island divertors for stellarators is presented and is used to find divertors that meet heat load requirements determined by material limits. The algorithm uses just two initial conditions: two starting coordinates on the island separatrix chosen by the user. We leverage the simplicity of the algorithm to explore the divertor parameter space in a fixed magnetic equilibrium. Heat loads are approximated using the field line diffusion model implemented in the FLARE code. Divertor solutions that satisfy heat load requirements while maintaining a high power fraction captured are found using a parameter scan and a Bayesian optimization routine. The optimization finds divertors that perform the same as the parameter scan, but with a 75% reduction in computational cost. The resulting divertors satisfy heat load requirements across varying cross-field heat diffusivities. Optimization over various islands in the equilibrium shows that low-elongation islands are the easiest to find divertors that satisfy heat flux requirements. This algorithm presents a simple parameterization for island divertors and facilitates further physics and optimization studies.

Plasma Physics and Controlled Fusion

Effects of fusion-born alphas on MHD instabilities in burning plasmas with spin-polarized fuels

Yueqiang Liu

Plasma Physics and Controlled Fusion2 days agoPlasma & ConfinementAI, Modeling & Simulation

A new magnetohydrodynamic-kinetic hybrid model is developed with inclusion of an anisotropic (in the particle pitch) particle distribution for fusion-born alphas, for the purpose of modeling drift-kinetic effects of the latter on macroscopic instabilities in burning plasmas with spin-polarized (SP) deuterium-tritium (D-T) fuels. The new model is applied to numerically analyze both the internal kink (IK) and the resistive wall mode (RWM) stability, based on two ITER D-T scenarios. The adiabatic contribution of alphas generally destabilize the IK and the RWM, with the anisotropic model generally yielding a stronger destabilization compared to the isotropic counterpart. Partial stabilization of the IK mode is generally obtained with inclusion of the non-adiabatic resonance contributions (of various sorts) of alphas in the zero-orbit width approximation. Adding the finite-orbit width correction brings full stabilization of the mode. Destabilization of an IK-peeling branch is however computed, accompanied by a substantial modification to the mode eigenfunction by anisotropic alphas. Non-adiabatic contributions of alphas are also generally stabilizing for the RWM, independent of the assumed (isotropic versus anisotropic) particle distribution model. On the other hand, triggering of a high-frequency fishbone-like mode is found in the ITER 10 MA scenario with finite plasma flow, by the adiabatic contribution of alphas due to SP fuels.

Plasma Physics and Controlled Fusion

Characteristics of monotonic sheaths near a wall with grazing magnetic incidence

Alessandro Geraldini, Robert J. Ewart, Stephan Brunner, Felix Parra

We consider a magnetised plasma in contact with an absorbing planar wall, where the angle α between the magnetic field and the wall is small, α ≪ 1 (in radians), and the plasma is uniform in the directions tangential to the wall. The finite ratio γ of the characteristic electron gyroradius ρ e to the Debye length λ D , γ = ρ e /λ D, is retained via a grazing-incidence (α ≪ 1) gyrokinetic treatment [1,2]. Building on a previously developed iterative scheme [2,3] to solve for the steady-state electrostatic potential in the quasineutral magnetic presheath of width ∼ ρ S , we developed a scheme that simultaneously solves for both the presheath and the non-neutral Debye sheath of width ∼ λ D in the limit λ D /ρ S → 0, provided that the electrostatic potential solution is monotonic. The code, called GYRAZE, thus provides the energy-angle distribution of ions at the wall and the velocity distributions of electrons reflected by the wall for different values of wall potential.

Plasma Physics and Controlled Fusion

Optimization of ARC-like tokamak stationary operation via core plasma composition and boundary shaping

Audrey Saltzman, Pablo Rodriguez-Fernandez, Aaron Ho, Garud Snoep, Jiyun Han, Jo Hall, Michail Savvas Anastopoulos Tzanis, Jon Hillesheim, Alexander J Creely, Philip B Snyder, et al.

Plasma Physics and Controlled Fusion2 days agoPlasma & ConfinementAI, Modeling & Simulation

Impurity composition, plasma shape, and pedestal density all provide strong levers on fusion power. Here, we explore the ways in which their variation changes fusion power and seek to find the optimum of these parameters. The key impacts of these variables are through changes in the core turbulent transport, the density of the fuel species, the pedestal pressure, and the plasma volume. ITG stabilization due to increased amounts of impurities is observed. The dependence of all of these parameters on the pedestal pressure is especially complicated because of the separate impacts on the peeling and ballooning modes, which can each limit the pedestal. Optimization of this multidimensional operating space is enabled by the use of Bayesian optimization, resulting in an operating point similar to ARC V3A with ∼30% more fusion power and a higher fusion power density. Increased shaping parameters, including elongation, triangularity, and squareness are all beneficial, as is high Zeff . When elongation is also allowed to vary, a ∼65% increase in fusion power can be achieved. While not commonly considered, we find squareness is an important lever on fusion power. The plasma performance is limited by the Greenwald density limit constraint. The workflow developed here and demonstrated with the example of ARC V3A can readily be applied to other tokamak designs.

Plasma Physics and Controlled Fusion

Real-Time Monitoring of Deuterium-Tritium Fusion Neutron Production for Fusion–Fission Hybrid Reactors Based on Reversed-Field Pinch Plasmas

Lidia Piron, Marco Gobbin, Nicolò Ferron, Matteo Baruzzo, Eric Fredrickson, Zamir Ghani, Krassimir K. K Kirov, Morten Lennholm, Roberto Piovan, P Martin

Plasma Physics and Controlled Fusion2 days agoPlasma & ConfinementControl & DiagnosticsAI, Modeling & Simulation

Results from the last DD and DT JET campaigns in the framework of the EUROfusion Tokamak Exploitation Work Package Activity" 2026 submitted to Nuclear FusionIn this work, we present a real-time algorithm for use in fusion-fission hybrid reactors to monitor the fast neutron production (neutron rate) generated by Deuterium-Tritium fusion reactions. The algorithm, based on insights from TFTR and JETD-Tritium operations, tracks continuously the neutrons 14.1 MeV. If this metric falls below a threshold value, due, for example, to fuel dilution, the onset of MHD instabilities or temporary actuator unavailability, the algorithm can raise an alarm. This enables plasma recovery when actuator capability permits, or ensures safe plasma termination when recovery is not feasible. The role of alpha particles is examined through test cases of the algorithm, while their confinement properties are investigated using the ORBIT code under various RFP magnetic field configurations.

Plasma Physics and Controlled Fusion

Control of Runaway Electron Current by Magnetic Chaos During Reconnection in Post-Disruption Plasmas

DARIO BORGOGNO, Daniela Grasso, Lovepreet Singh

Plasma Physics and Controlled Fusion2 days agoPlasma & ConfinementControl & DiagnosticsAI, Modeling & Simulation

We numerically investigate the mutual interaction between runaway electron (RE) current and magnetic reconnection in a post-disruption plasma configuration where the plasma current is entirely carried by REs. Extending previous two-dimensional studies to full three-dimensional geometry, we show that the presence of RE current enhances the reconnection process, resulting in a reconnected area approximately 50% larger than in the absence of REs. In the 3D regime, the nonlinear interaction among multiple unstable tearing modes with different helicities drives the development of magnetic chaos, which rapidly spreads from the island separatrices to the entire reconnected region. Once global chaos is established, the chaotic magnetic field lines efficiently redistribute the RE current, leading to a progressive flattening of its radial profile. This occurs over a timescale of approximately 300τ A , corresponding to approximately 10µs for typical JET parameters, in quantitative agreement with experimental observations. These results provide a consistent physical framework for interpreting RE redistribution and loss in post-disruption plasmas, with direct implications for disruption mitigation strategies in future high-current devices such as ITER.

Plasma Physics and Controlled Fusion

On the timescales of controlled termination of tokamak plasmas

Simon Van Mulders, Olivier Sauter

Plasma Physics and Controlled Fusion2 days agoPlasma & ConfinementControl & DiagnosticsAI, Modeling & Simulation

The RAPTOR code is used to model how the time required for controlled termination of Ohmic plasmas scales from present tokamaks like TCV and JET, to reactor-grade tokamaks like ITER and DEMO. We show that ramping the plasma current Ip down to 20% of the flat-top value over a time Δt ramp−down =τLR=Li/R, with internal inductance Li and resistance R evaluated at flat-top conditions, results in an approximately self-similar peaking of the current density for these four tokamaks, indicating the adequacy of τLR as a relevant timescale for cross-machine comparison, yielding τLR= 0.033s (TCV), 2.87s (JET), 63.2s (ITER) and 166.9s (DEMO). Note that τLR is easy to evaluate, both in systems codes and on a real-time control system. For the simulated ramp-downs with Δt ramp−down =τLR, the end-of-ramp-down normalized internal inductance ℓi3 is limited below 2. An Ip ramp-down faster than τLR=Li/R requires a reversal of the boundary loop voltage and leads to the formation of a broad plasma layer carrying current in the direction opposite to the total plasma current, concomitant with ℓi3>2, a central region with low magnetic shear and strongly peaked pressure profiles. Significant reduction of plasma volume and elongation, as foreseen for ITER and DEMO, is shown to counteract the reversal of current density and the ℓi3 increase, while easing vertical stability control, potentially enabling faster Ip ramp-down scenarios. Experimental and theoretical studies should be performed to test the feasibility of such fast termination scenarios, notably with respect to vertical position control, shape control and (resistive) beta limits. An analytical model is proposed to estimate τLR based on 0D engineering parameters. For burning plasmas, ITER baseline simulations show that a termination within 150% of the L-mode τLR can avoid negative edge current density and a large ℓi3 increase for an HL transition 1/3rd into the ramp-down.

Plasma Physics and Controlled Fusion

Numerical study on the effects of conducting wall geometry and plasma toroidal rotation on resistive wall mode in CFETR

Yu Jing, Shilong Li, Yue Liu

Plasma Physics and Controlled Fusion2 days agoPlasma & ConfinementAI, Modeling & Simulation

Based on a 13 MA hybrid equilibrium of the CFETR tokamak, the MARS code is employed to investigate the effects of conducting wall geometry and plasma toroidal rotation on resistive wall mode (RWM) stability. Realistic wall configurations with localized geometric modifications on the low-field side (LFS), high-field side (HFS), and upper and lower poloidal ends are considered, together with a sheared toroidal rotation profile relevant to the CFETR 13 MA hybrid scenario and a uniform rotation profile for comparison. The results show that wall geometry variations on the LFS have a more significant influence on RWM stability than modifications in other wall regions, and RWM stability is highly sensitive to plasma toroidal rotation. To clarify the role of rotation-profile structure, several sheared rotation profiles with different peak positions and radial widths are designed and analyzed. Across the uniform-rotation case and the designed sheared-rotation cases, elongation of the LFS conducting wall reduces the critical rotation frequency required for RWM stabilization relative to the conformal and actual conducting wall configurations. These results indicate a coupling between LFS conducting wall geometry and plasma rotation in determining the RWM stability boundary in the CFETR 13 MA hybrid scenario.

arXiv (physics.plasm-ph)

Reaching high fusion gain with grams of spin-polarized fuel

J. F. Parisi

Building on recent ignition-access work of Delgado-Aparicio, Ono, and Menard, we show that even a single-use, gram-scale quantity of spin-polarized fuel (SPF) is useful for increasing fusion power and gain in magnetic confinement fusion machines such as tokamaks and stellarators. While fueling a fusion power plant continuously with SPF requires $\sim$kilograms per day, far beyond present capabilities, a single-use short pulse of SPF allows a fusion plasma to cross into a high-gain regime, and stay there, even after switching back to regular unpolarized fuel. With continuous polarized fueling, polarization also makes high-gain plasmas easier to control: a resonant wave that depolarizes the fuel lowers the reactivity quickly, on a much faster timescale than transport. Grams of polarized fuel can therefore improve plasma performance and open a path to scaling SPF sources and usage, from small first experiments to continuous fueling.

arXiv (physics.plasm-ph)

Compressional heating above 1 keV on the LM26 magnetized target fusion machine

S. J. Howard, D. Krotez, P. Carle, J. Sanchez Rojo, R. Underwood, A. Froese, M. Reynolds, N. Sirmas, K. Conquergood, K. Epp, et al.

arXiv (physics.plasm-ph)2 days agoPlasma & ConfinementInertial Fusion & HEDP

The LM26 device has achieved a peak electron temperature of $T_e = 1180 \pm 65$ eV as measured by filtered X-ray diodes, supported by adjacent Thomson scattering measurements of $T_e = 1090 \pm 40$ eV, with a deuterium ion temperature of $T_i = 459 \pm 33$ eV as inferred from neutron yield. LM26 compresses a spherical tokamak plasma inside an initially 1.76 m diameter solid lithium liner imploded by theta-pinch coils. Radial compression by a factor of 2.75 increases $T_e$ over fivefold, while $T_i$ increases as much as twofold. The integrated observation of magnetic flux compression, electron heating, ion heating, and neutron production in a magnetized plasma compressed by a large lithium liner is an important milestone for magnetized target fusion

Plasma Physics and Controlled Fusion

AI-Accelerated Gyrokinetic Predictions of Turbulent Transport for Stellarator Design Optimization and Experimental Planning

R. Michael Churchill, Matt Landreman, Jong Youl Choi, Byoungchan Jang, Rory Conlin, Noah Mandell, Anima Anandkumar, Valentin Duruisseaux, Jeffrey Larson, Dario Panici, et al.

Plasma Physics and Controlled Fusion2 days agoPlasma & ConfinementAI, Modeling & Simulation

Previous work built AI-based surrogates for a nonlinear gyrokinetic simulation code with the goal of using them for fast, direct calculations of turbulent ion heat flux in stellarator design optimizations and scenario planning for experiments. These AI surrogates were trained on data from >200k nonlinear, adiabatic electron gyrokinetic simulations with the gyrokinetic flux-tube code GX, using a wide range of stellarator magnetic configurations ($\sim$23k), positions in the plasma, and gradient scale lengths. In this paper, we demonstrate the use of the AI-based turbulence surrogate in the optimization of stellarator magnetic equilibrium and to speed up stellarator transport solvers. Due to its speed ($\sim$ms), the AI-based surrogate enables previously unattainable optimization objectives, such as full radial profiles of ion turbulent heat flux, or directly optimizing to maximize the turbulent critical gradient at multiple locations across the plasma. These direct calculations provide a potentially more accurate optimization target and reduce reliance on ad-hoc heuristics that may not accurately capture the variation of turbulent transport with magnetic configuration. By including the AI-based surrogate for turbulent heat flux in a transport solver, we can quickly postprocess and confirm the improved ion temperature resulting from the optimized equilibrium. Finally, we demonstrate the use of AI agents with strong reasoning AI models to automate the outer loop, exploring many objective and hyperparameter configurations with this AI-based turbulence surrogate to discover improved turbulence optimized magnetic equilibria.

Oct 7

Nuclear Fusion

Effects of tungsten radiative cooling on impurity, heat and momentum transport in DIII-D plasmas

Arsene Stephane Tema Biwole, Tomas Odstrcil, Xavier L Litaudon, Shengyu Shi, Darin R Ernst, Carl Friedrich Benedikt Zimmermann, Jeff B Lestz, Nathan T Howard, Pablo Rodriguez-Fernandez, Filipp Khabanov, et al.

Nuclear Fusion3 days agoPlasma & Confinement

A first-of-its-kind experiment was conducted in the DIII-D tokamak under WEST similarity constraints on plasma shape and core parameters. This work presents a detailed transport study comparing a reference regime dominated by intrinsic carbon radiation and a high-radiation regime resulting from controlled tungsten (W) injection using the Laser Blow-Off system, with a core tungsten concentration n W /n e ~ 3×10 −4 and a radiated-power fraction f rad > 0.5. The W-induced radiative cooling lowered the electron temperature, thereby decreasing T e /T i and stabilizing trapped-electron-mode (TEM) turbulence. This transition in turbulence regime reduced momentum and ion thermal diffusivities, yielding ion temperature peaking and a factor-of-two increase in toroidal rotation. At the outer plasma region, enhanced E×B shear and increased collisionality further suppressed ion-scale turbulence, causing a sharp drop in ion heat flux. Consequently, impurity transport, predominantly turbulent in the low-radiation regime, acquired a strong neoclassical inward W convection during radiative cooling, bootstrapping the cooling cycle. Despite f rad > 0.5, radiative collapse was not observed, likely owing to collisional ion-to-electron energy exchange acting as an electron-energy reservoir, together with 1/1 MHD activity modulating the radiated power through core impurity neoclassical T i -screening. These results support preparation for a tungsten wall change in DIII-D by elucidating tungsten-induced turbulence stabilization. They also provide key insights for interpreting plasma performance in WEST and are relevant to future reactors expected to operate with radiating tungsten-walled plasmas.

Oct 6

arXiv (physics.plasm-ph)

Numerical error analysis of EMC3-EIRENE simulations in the HSX stellarator

F. A. Chavarria, D. Boeyaert, H. Frerichs, K. A. Garcia, B. Geiger

arXiv (physics.plasm-ph)4 days agoPlasma & ConfinementAI, Modeling & Simulation

Plasma edge simulations with codes like EMC3-EIRENE are widely used to study fusion magnetic confinement devices. However, numerical errors can significantly impact the simulation solution and are often insufficiently characterized. These errors consist of the statistical error, bias, and time integration error, resulting from the finite sampling and tracking of Monte Carlo particles, and the discretization error, resulting from a finite grid resolution. This work presents the first comprehensive numerical error analysis of EMC3-EIRENE simulations in stellarator geometries, focusing on edge plasmas in the Helically Symmetric eXperiment (HSX). Fundamental plasma and neutral quantities are analyzed, and error reduction rates are compared against theoretical expectations. The statistical error, bias, and time integration error are fully characterized; however, quantification of the discretization error remains challenging because of the complex grid geometries used in EMC3-EIRENE. The commonly used volume averaged relative change metric is shown to systematically underestimate the statistical error, highlighting a critical flaw in EMC3-EIRENE analysis, where convergence is claimed despite significant noise remaining in the simulation solution. Dominant contributions of the time integration error are shown to differ in stellarator simulations compared to tokamak simulations, related to the relative importance of cross-field transport between the two devices. Based on these results and existing literature, we establish best practices towards improved accuracy and efficiency in general stellarator modeling with EMC3-EIRENE.

Plasma Physics and Controlled Fusion

Effects of neoclassical toroidal viscosity on plasma flow evolution in the presence of resonant magnetic perturbation in a tokamak

Fangyuan Ma, Ping Zhu, Jiaxing Liu

Plasma Physics and Controlled Fusion4 days agoPlasma & Confinement

Effects of neoclassical toroidal viscosity (NTV) on plasma flow evolution in the presence of resonant magnetic perturbation (RMP) in a tokamak have been evaluated using a cylindrical theory model. Calculations indicate that the introduction of NTV barely alters the original locked or unlocked flow states at the resonant surface for an RMP amplitude of about 4 × 10−4 T, but significantly suppresses the core convective frequency −k · u from plasma flow. Here, k is the wave vector of the propagating island and u is the plasma velocity. As the ratio of plasma thermal pressure to magnetic pressure, i.e. β increases, the amplitude of the NTV torque is enhanced, which can either decelerate or accelerate the plasma flow, and thus alter the electromagnetic (EM) torque via the island phase. The combined interplay of NTV and EM torques ultimately sustains the original flow state at the resonant surface in the presence of RMP.

Plasma Physics and Controlled Fusion

Sensitivity of a low-shear heliotron configuration to localised ferritic-steel perturbations

Akinobu Matsuyama, Fumiya Tanji, Yuji Nakamura, Shigeru Inagaki, Yusuke Yamashita, Akihisa Yamamoto, S Kobayashi, Fumiyoshi Kin, Shinichiro Kado, Shinichiro Inagaki, et al.

Plasma Physics and Controlled Fusion4 days agoPlasma & ConfinementAI, Modeling & Simulation

The influence of ferritic steel on low-shear stellarator/heliotron magnetic configurations is investigated for the Heliotron J device using a point dipole magnetisation model. By numerically evaluating ferritic steel plates assumed at several locations inside the Heliotron J vacuum vessel, the changes in the rotational transform and magnetic island width are shown to be sensitive to the installation location. This location sensitivity arises from the toroidal variation of poloidal mode coupling between the background nonaxisymmetric field and ferritic-steel perturbation, rather than being determined solely by the perturbation amplitude. The resulting mode coupling can enhance the resonant vacuum magnetic perturbation at specific locations. Ferritic steel plates placed on the outer side of a straight section produce the most significant changes in the magnetic topology and exhibit the highest sensitivity to violations of the $M=4$ toroidal periodicity. Additionally, we show that appropriate arrangements of passive magnetic dipoles can reduce the effective helical ripple while preserving the vacuum magnetic well depth in Heliotron J, and can induce a stellarator-asymmetric boundary perturbation in low-field experiments.

arXiv (physics.plasm-ph)

Fast-ion effects on $E\times B$ staircase organization and the heat-flux response to the ion-temperature gradient

Il-Hwan Kim, Jaemin Seo

arXiv (physics.plasm-ph)4 days agoPlasma & ConfinementAI, Modeling & Simulation

Zonal-flow organization can modify the relation between heat flux and temperature gradient, but how fast ions affect this organization and the accompanying transport response remains less well characterized. We use nonlinear, global gyrokinetic simulations based on KSTAR fast-ion-regulated enhancement (FIRE) mode to compare cases with and without fast ions during profile relaxation across five initial main-ion temperature gradients. We observe that fast ions induce larger zonal-flow and shearing-rate amplitudes, together with persistent shear layers. At the reference profile based on the experiment, these shear layers coexist with temperature-gradient corrugations qualitatively consistent with $E\times B$ staircases. When fast ions are present, inward and outward ion heat fluxes coexist at different radii, which causes the average heat flux to be smaller than when fast ions are absent. This redistribution of ion heat transport may be relevant to understanding the improved ion confinement observed in FIRE mode. In particular, we note a transition-like response in the presence of fast ions, whereby the heat flux decreases as the ion-temperature gradient increases, in contrast to the conventional Fick's law trend without fast ions. This behavior that deviates from Fick's law suggests that FIRE mode may represent a bifurcation to a distinct transport regime rather than a continuous high-performance extension of L-mode. These findings highlight the importance of the initial temperature gradient and global zonal-flow organization when assessing fast-ion effects on ion heat transport.

Publication Alerts

Get the latest fusion research papers delivered to your inbox.

Email *