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S. J. Diem

Publications and source records attributed to S. J. Diem.

2 recordsLinked to original sources

Design of a multifunctional Doppler backscattering diagnostic for the Pegasus-III Experiment

The Doppler backscattering (DBS) diagnostic measures flows and electron density fluctuations. Recent work indicates that DBS can also infer the magnetic pitch angle (Yeoh et al., NF 2026). We present the preliminary design of a DBS for the Pegasus-III Experiment. This DBS will serve two objectives. First, it will advance diagnostic science, by supporting understanding of the DBS instrumentation functions, using DBS to constrain the magnetic equilibrium, and data-driven inference of plasma properties from DBS signals. Secondly, it will support Pegasus-IIIs research directions, such as solenoid-free plasma initiation and O-X-B mode conversion for heating and current drive, since density fluctuations affect mode conversion efficiency and pitch angle measurements can be used to locate the mode conversion window. This ex-vacuum DBS system uses a single channel, tuneable Ka-band source, a corrugated horn antenna, and a homodyne I/Q receiver with baseband digitization. For greater flexibility, which is especially important for pitch angle measurements, the quasioptical elements include a rotatable spinner for O- and X-mode selection and a mirror with 2D steering. Using the \textit{Scotty} beam-tracing code, for a range of poloidal launch angles $8^\circ$ to $18^\circ$ and a corresponding toroidal launch angle between $0^\circ$ to $3^\circ$ for maximal backscattered DBS power, we find that the DBS system is capable of measuring ion-scale density fluctuations $1\leq k_{\perp,c} \leq8 \text{ cm}^{-1}$ at a range of normalized radial coordinates from the outer core ($ρ\sim 0.65$) to just beyond the last-closed flux surface (LCFS), where $ρ=0$ corresponds to the magnetic axis and $ρ=1$ the LCFS. The system is also designed with additional toroidal steering capability, $-4^\circ$ to $8^\circ$, to resolve the toroidal response needed for magnetic pitch angle measurements.

physics.plasm-ph

Modeling of Injected Current Stream-Induced 3D Perturbations in Local Helicity Injection Plasmas

Solenoid-free tokamak startup techniques are essential for spherical tokamaks and offer a pathway to cost reduction and design simplification in fusion energy systems. Local helicity injection (LHI) is one such approach, employing compact edge current sources to drive open field line current that initiates and sustains tokamak plasmas. The recently commissioned Pegasus-III spherical tokamak provides a platform for advancing this and other solenoid-free startup methods. This study investigates the effect of LHI on magnetic topology in Pegasus-III plasmas. A helical filament model represents the injected current, and the linear plasma response to its 3D field is calculated with M3D-C1. Poincaré mapping reveals substantial flux surface degradation in all modeled cases. The onset of overlapping magnetic structures and large-scale surface deformation begins at $Ψ_{N} \approx 0.37$, indicating a broad region of perturbed topology extending toward the edge. In rotating plasmas, both single-fluid and two-fluid models exhibit partial screening of the $n = 1$ perturbation, with two-fluid calculations showing stronger suppression near the edge. In contrast, the absence of rotation leads to strong resonant field amplification in the single-fluid case, while the two-fluid case with zero electron rotation mitigates this amplification and preserves edge screening. Magnetic probe measurements indicate that modeling the stream with spatial spreading$-$representing distributed current and/or oscillatory motion$-$better reproduces measured magnetic power profiles than a rigid filament model. The results underscore the role of rotation and two-fluid physics in screening stream perturbations and point to plasma flow measurements and refined stream models as key steps toward improving predictive fidelity.

physics.plasm-ph