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REVIEW 3 major objections 5 minor 41 references

Electromagnetic System Conceptual Design for a Negative Triangularity Tokamak

T0 review · 3 major / 5 minor · reviewed 2026-08-10 · deepseek-v4-flash

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Pith's one-line read A compact negative-triangularity tokamak for testing plasma control software can be built with existing copper magnet technology, with an eight-coil poloidal set covering the target shaping space and passive plates cutting vertical…

desk verdict A credible, internally consistent pre-conceptual design for a dedicated NT testbed; the vertical-stability case leans on an idealized wall model that needs 3D verification. read the letter →

arxiv 2501.14682 v2 pith:KZSFK2B6 submitted 2025-01-24 physics.plasm-ph

Sophia Guizzo , Mikhail A. Drabinskiy , Christopher Hansen , Aleksandr G. Kachkin , Eduard N. Khairutdinov , Andrew O. Nelson , Maxim R. Nurgaliev , Matthew Pharr
show 2 more authors
Georgy F. Subbotin Carlos Paz-Soldan
This is my paper · ORCID
classification physics.plasm-ph
keywords negativetriangularitytokamakelectromagneticdesignpoloidalfieldcoilsverticalstabilitypassivestabilizingplatesTokaMakertoroidalcoildisruptionforces
verification ladder T0 review T1 audit T2 compute T3 formal

The pith

A machine-rendered reading of the paper's core claim, the machinery that carries it, and where it could break.

The reading

This paper tries to establish that a small, dedicated negative-triangularity (NT) tokamak can be built today from conventional copper magnet technology, and that it can serve as a testbed for the control software that future fusion pilot plants will need. Using the TokaMaker Grad–Shafranov solver, the authors show that eight poloidal-field coils plus a central solenoid can access the full target window of plasma shapes ($-0.7 < \delta < -0.3$, $1.5 < \kappa < 1.9$) at 0.75 MA of plasma current. Because strong NT and high elongation drive vertical instability, the design adds high-field-side and low-field-side passive copper plates, which together reduce vertical instability growth rates by about 75% and bring most geometries within reach of active feedback control. The paper also bounds the forces on coils and passive structures during normal operation and current quenches, and specifies a 16-coil demountable copper toroidal-field system providing 3 T on axis. If these claims hold, a compact NT experiment can move to detailed engineering as a platform for validating real-time plasma control.

What carries the argument

The load-bearing machinery is the feedback capability parameter $\gamma\tau_W$, the product of the vertical instability growth rate $\gamma$ and the wall diffusion time $\tau_W$, which is used as the controllability metric, together with the TokaMaker Grad–Shafranov solver that computes equilibria, stability eigenmodes, and forces for each candidate geometry. The design's two workhorse elements are the eight-coil poloidal-field set plus three-section central solenoid, which generates the full shaping window, and the passive copper stabilizing plates placed on both the high-field and low-field sides of the plasma, which reduce $\gamma\tau_W$ by about 75% across most of the scan. The toroidal-field system is carried by a specific mechanical design: 16 demountable three-turn copper coils with 313 kA per turn, a jointed case, and a steel shell that resists the roughly 6,000 kN·m overturning torque.

What would settle it

Recompute the vertical instability growth rate $\gamma\tau_W$ for the actual as-built vacuum vessel geometry (non-conformal, with ports) with the proposed passive plates for the baseline $\delta = -0.5$, $\kappa = 1.7$ scenario; if $\gamma\tau_W$ stays above about 8, the paper's claim that passive plates bring most geometries within active control fails.

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Extended reading notes

Core claim

The central claim is that a purpose-built negative-triangularity tokamak, the NTT with $R_0 = 1$ m, $a = 0.27$ m, $B_t = 3$ T, and $I_p = 0.75$ MA, can meet all of its electromagnetic requirements with conventional copper magnets. The poloidal-field system, four up-down-symmetric coil pairs plus a three-section central solenoid, reproduces every combination of triangularity and elongation in the target window $-0.7 < \delta < -0.3$ and $1.5 < \kappa < 1.9$ at full plasma current, with maximum coil currents near 1 MA. Vertical stability, the main physics risk for strongly shaped NT plasmas, is addressed with low-field-side and high-field-side passive copper plates: in the idealized conducting-wall model used for the stability scans, the plates cut the growth rate of the $n = 0$ vertical mode by roughly 75%, moving the feedback capability parameter $\gamma\tau_W$ from uncontrollable values (often infinite with the real vacuum vessel alone) into a range where most geometries are actively controllable. The same models bound the peak forces on toroidal and poloidal coils and the disruption loads on the vacuum vessel and plates, all judged within structural feasibility. The toroidal field of 3 T is produced by 16 demountable three-turn copper coils carrying 313 kA per turn, with joints that allow maintenance of the vacuum vessel and inner poloidal coils. The intended upshot is that a compact NT experiment can be built with existing technology to test and mature the control software that reactor-scale devices will depend on.

Load-bearing premise

The vertical-stability results assume a simplified 1 cm thick stainless steel vacuum vessel that hugs the plasma shape at a 10 cm distance; if the real, non-conforming vessel with its ports and gaps weakens the passive plates' effect, then the claimed 75% growth-rate reduction and the controllability of the final design are not established.

Editorial extensions

If this is right

  • A dedicated NT tokamak testbed can be built with present-day copper magnet technology rather than superconducting magnets, reducing cost and engineering risk for a control-software validation platform.
  • The eight-coil PF set with a three-section CS reaches the full $-0.7 < \delta < -0.3$, $1.5 < \kappa < 1.9$ geometry window at 0.75 MA, so control algorithms can be exercised across a wide, reactor-relevant shaping space.
  • With both high-field-side and low-field-side passive plates, $\gamma\tau_W$ drops by roughly 75%, bringing most target geometries within the range of active vertical control systems.
  • The predicted peak coil forces and current-quench loads on passive structures stay within structural feasibility, establishing upper bounds for the mechanical design of supports.
  • Demountable three-turn copper TF coils achieve 3 T with 1% ripple and open the machine for maintenance; the roughly 45 tons of copper is a practical, conventional magnet plant.

Reading between the lines

Editorial extensions of the paper, not claims the author makes directly.

  • This page's own reading: the vertical-stability study optimizes the passive plates against an idealized 1 cm conformal stainless steel wall, and the paper does not demonstrate that the same ~75% growth-rate reduction survives on the as-built, non-conformal vacuum vessel with ports and gaps; that re-optimization is an evident next step.
  • If the reduction does survive, the spread in $\gamma\tau_W$ across the geometry scan is a design feature: a control testbed benefits precisely from having both easily and marginally controllable configurations to exercise algorithms.
  • The 4.0° outer strike-point incidence angle at the most negative triangularity suggests divertor heat loads could become a constraint at the edge of the design window, even though NT's larger wetted area helps overall.
  • The POPCON results imply the NTT would reach central ion temperatures of about 2.5 keV Ohmically and 3 keV with 3 MW of auxiliary power, which would make it not only a controls testbed but a small physics platform for NT scenarios.
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Editorial analysis

A structured set of objections, weighed in public.

Desk editor's note, referee report, and a circularity audit.

Referee Report

3 major / 5 minor

Summary. The paper presents a pre-conceptual electromagnetic design for a compact negative triangularity tokamak (NTT) with R0 = 1 m, a = 0.27 m, Bt = 3 T, Ip = 0.75 MA. Using the TokaMaker Grad-Shafranov code, it proposes a poloidal-field system of eight coils plus a three-section central solenoid, claims access to the target shape domain (−0.7 < δ < −0.3, 1.5 < κ < 1.9), analyzes vertical stability with passive stabilizing plates, estimates coil and disruption forces, and describes a 16-coil demountable copper TF system. A POPCON analysis is included to support the stated performance targets. The authors explicitly label the work as pre-conceptual and acknowledge several open items, including self-consistent pulse simulation and higher-fidelity structural modeling.

Significance. If the results hold, the NTT design would be a useful reference point for a compact, copper-coil negative triangularity device aimed at control-software development. The study's strengths are its systematic use of an open-source equilibrium code, explicit scans over the target shape space, a direct assessment of vertical instability, and honest caveats about pulse simulations and structural modeling. The central claim that the required capabilities can be realized with existing copper magnet technologies is plausible, but it rests on two areas that need stronger evidence: vertical-stability margins under realistic vessel geometry and plate segmentation, and CS flux/pulse consistency. The paper also makes useful, falsifiable quantitative predictions about coil currents, growth-rate reduction, and force magnitudes that can guide detailed engineering.

major comments (3)
  1. [Section 3, Figure 5] The vertical-stability conclusion rests on a model substitution that is not shown to be representative. The actual vacuum vessel (τW ≈ 5.8 ms) is reported to give effectively infinite growth rates for most of the target shape space, after which the plate optimization is performed on a 1 cm thick stainless-steel vessel conformal to the plasma at 10 cm (τW ≈ 17 ms). The final figure returns to the original vessel but remains axisymmetric and assumes toroidally continuous plates, even though the plates must be segmented and compatible with ports. Because the unstabilized growth rate is effectively infinite, the entire control margin is created by the plates; 3D effects such as port openings, flange joints, or plate segmentation could push γτW above the ~8 controllability threshold in the corners of the scan. Please provide a 3D eddy-current sensitivity study (e.g., ThinCurr) or a plate-resistance/coverage perturbation scan, and state explicitly in the abstract/conclusions that vertical-stability feasibility is contingent on the idealized wall geometry.
  2. [Section 2, Table 2] The CS segment current is fixed at −3 MA, with the parenthetical note that 'self-consistent pulse simulations are in progress.' Since the device targets a 10 s pulse length, this leaves the scenario-accessibility claim as an equilibrium-statics statement only. The maximum coil currents and the ability to reach Ip = 0.75 MA across the shape scan are computed without a flux-consumption or current-trajectory check, so the design does not yet demonstrate an actual discharge that attains the stated conditions. Please include a start-up/ramp-down/current-hold simulation, or explicitly narrow the claim to 'equilibrium accessibility' rather than full scenario realization.
  3. [Section 4 and Section 5.1] The force calculations are presented as upper limits, but no structural allowables or stress margins are provided. For example, the net torque on a TF coil is quoted as ≈6,000 kN-m and the total deformation as ≤5 mm, but the supporting structural analysis and material allowables are not shown; similarly, the passive plates are said to require 'significantly increased structural support' without a quantitative feasibility check. Since the abstract claims the design is realizable with existing technologies, please either add stress/yield checks for the major components or soften the claim to 'forces have been bounded; structural design remains to be completed.'
minor comments (5)
  1. [Section 6] The text says 'Additional axillary heating'; this should be 'auxiliary heating'.
  2. [Introduction] 'preventing the occurence' should be 'preventing the occurrence'.
  3. [Section 3, Figure 5] Figure 5 lacks a visible colorbar or numerical labels. Please add one so the claimed γτW values, especially the threshold near 8, can be read from the figure.
  4. [Section 3] The phrase 'feeedback capability parameter' appears to be a typo for 'feedback capability parameter'; please standardize the terminology.
  5. [Section 4 and Section 5.1] The text states '3 T is achieved with 313 kA in each coil' in Section 5.1, while Section 4 uses 939 kA per TF coil. Since each TF coil has three turns, the statements are consistent but should be cross-referenced to avoid an apparent contradiction.

Circularity Check

0 steps flagged · score 0.0 of 10

No significant circularity: coil currents, growth rates, and forces are computed outputs of Grad-Shafranov and eddy-current models, not fitted to reproduce the target claims.

full rationale

The derivation chain is self-contained in the engineering-design sense. The PF coil locations and maximum currents in Table 2 are outputs of a TokaMaker equilibrium scan over the target delta-kappa grid, not inputs chosen to force the geometry-coverage claim. The vertical-stability results are computed by solving the linearized n=0 eigenproblem for specified conducting structures; the approximate 75% reduction in gamma*tau_W is the outcome of a plate-location optimization, not a fitted parameter renamed as a prediction. The TF current (313 kA per turn, 939 kA per three-turn coil) is calculated from the 3 T on-axis field requirement. Disruption loads follow from a linear current ramp with a quench time taken from the ITPA disruption database. Self-citations to TokaMaker [26], the NT vertical-stability assessment [25], and the DIII-D NT scaling law [1] supply tools and empirical inputs; none is defined in terms of the present target results, and the high-field-side plate benefit cited from [25] is independently re-derived in the present scan on the conformal-vessel model. The idealized 1 cm thick conformal vessel used in Section 3 is an acknowledged modeling assumption: the paper states the actual vacuum vessel gives near-infinite growth rates, labels the conformal-vessel cases separately from the final vessel with plates, and notes the vessel will undergo further design iterations. Any concern about port openings or 3D eddy-current closure is therefore a robustness limitation of the analysis, not a circular reduction. No equation in the paper reduces to its own input by construction.

Assumptions & free parameters 4 free parameters · 4 assumptions · 0 invented entities

The design relies on several chosen inputs: target device parameters, a fixed CS current, an idealized vacuum vessel for stability, a current quench time, and confinement scaling assumptions. The central feasibility claim is therefore conditional on these choices; none are fitted to data by this paper, but they are also not independently validated here.

free parameters (4)
  • Target device parameters = R0=1 m, a=0.27 m, Bt=3 T, Ip=0.75 MA, pulse 10 s
    Stated design targets selected to match performance objectives; they are inputs, not outputs of the design calculation.
  • Central solenoid segment current = -3 MA (fixed)
    CS current is fixed at -3 MA for all shape scans; self-consistent pulse trajectories are listed as future work, so accessible-geometry and force results depend on this choice.
  • Passive plate geometry = Not stated (plate positions and thickness from manual stability study)
    Plate locations and thickness are optimized but not tabulated; the 75% growth-rate reduction depends on this unspecified geometry.
  • Confinement quality H98,y2 = 1
    POPCON uses H98,y2=1 and the NT scaling from DIII-D; this is an assumed performance level, not a measured one.
assumptions (4)
  • standard math Grad-Shafranov equilibrium solved by TokaMaker adequately models the axisymmetric plasma and coil fields.
    Invoked throughout Sections 2-4; the code is published, but this paper does not include validation data for the specific NTT geometry.
  • ad hoc to paper A 1 cm thick stainless steel vacuum vessel conformal to the plasma at 10 cm is representative enough for stability and plate optimization.
    Section 3: adopted after the actual vessel gives infinite growth rates; direct evidence that the real vessel behavior is not computed.
  • domain assumption The 0.65 ms current quench time from the ITPA disruption database applies to NTT.
    Section 4: used to compute disruption forces; multi-machine scaling may not capture this specific compact device.
  • domain assumption NT confinement scaling from DIII-D and H98,y2=1 bound the achievable performance.
    Section 6: the power-balance POPCON depends on these scaling choices; no independent confinement prediction is provided.

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Cite this review

Pith. "Pith review of Electromagnetic System Conceptual Design for a Negative Triangularity Tokamak." pith.science (2026). https://pith.science/paper/KZSFK2B6

@misc{pith2026250114682,
  author       = {Pith},
  title        = {Pith review of: Electromagnetic System Conceptual Design for a Negative Triangularity Tokamak},
  year         = {2026},
  howpublished = {\url{https://pith.science/paper/KZSFK2B6}},
  note         = {Machine review of arXiv:2501.14682}
}
abstract

Negative triangularity (NT) tokamak configurations have several key benefits including sufficient core confinement, improved power handling, and reduced edge pressure gradients that allow for edge-localized mode (ELM) free operation. We present the design of a compact NT device for testing sophisticated simulation and control software, with the aim of demonstrating NT controllability and informing power plant operation. The TokaMaker code is used to develop the basic electromagnetic system of the $R_0$ = 1 m, $a$ = 0.27 m, $B_t$ = 3 T, $I_p$ = 0.75 MA tokamak. The proposed design utilizes eight poloidal field coils with maximum currents of 1 MA to achieve a wide range of plasma geometries with $-0.7 < \delta < -0.3$ and $1.5 < \kappa < 1.9$. Scenarios with strong negative triangularity and high elongation are particularly susceptible to vertical instability, necessitating the inclusion of high-field side and/or low-field side passive stabilizing plates which together reduce vertical instability growth rates by $\approx$75%. Upper limits for the forces on poloidal and toroidal field coils are predicted and mechanical loads on passive structures during current quench events are assessed. The 3 T on-axis toroidal field is achieved with 16 demountable copper toroidal field coils, allowing for easy maintenance of the vacuum vessel and poloidal field coils. This pre-conceptual design study demonstrates that the key capabilities required of a dedicated NT tokamak experiment can be realized with existing copper magnet technologies.

Figures

Figures reproduced from arXiv: 2501.14682 by the authors.

Figure 1
Figure 1. CAD visualization of the negative triangularity toka [PITH_FULL_IMAGE:figures/full_fig_p002_1.png] view at source ↗
Figure 2
Figure 2. NT tokamak cross-section with key components la [PITH_FULL_IMAGE:figures/full_fig_p003_2.png] view at source ↗
Figure 3
Figure 3. Baseline scenario with (a) δ = -0.7, (b) δ = -0.5, and (c) δ = -0.3 and corresponding poloidal field coil currents [PITH_FULL_IMAGE:figures/full_fig_p004_3.png] view at source ↗
Figures from the paper (8 more)
Figure 4
Figure 4. Figure 4: (a) Left-most, (b) central, and (c) right-most strike point locations with (d) corresponding poloidal field coil and divertor [PITH_FULL_IMAGE:figures/full_fig_p004_4.png]
Figure 5
Figure 5. Figure 5: Feedback capability parameter γτW across geometry scan for (a) a vacuum vessel conformal to the baseline geom￾etry, approximately 10 cm from the plasma boundary, (b) the same vacuum vessel with copper stabilizing plates, and (c), the final vacuum vessel design with cop…
Figure 6
Figure 6. Figure 6: (a) Maximum poloidal field and (b) resulting [PITH_FULL_IMAGE:figures/full_fig_p006_6.png]
Figure 7
Figure 7. Figure 7: (a) Radial and (b) vertical force densities on the [PITH_FULL_IMAGE:figures/full_fig_p006_7.png]
Figure 8
Figure 8. Figure 8: (a) Radial and (b) vertical force densities on the vacuum vessel, radial force densities on the (c) inner and (d) outer passive [PITH_FULL_IMAGE:figures/full_fig_p007_8.png]
Figure 9
Figure 9. Figure 9: (a) Full, 16 toroidal field coil assembly without sup [PITH_FULL_IMAGE:figures/full_fig_p007_9.png]
Figure 10
Figure 10. Figure 10: (a) Toroidal field coil in steel shell and (b) toroidal [PITH_FULL_IMAGE:figures/full_fig_p008_10.png]
Figure 12
Figure 12. Figure 12: Plasma OPerational CONtour for the Negative Tri [PITH_FULL_IMAGE:figures/full_fig_p009_12.png]

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Works this paper leans on

41 extracted references · 12 canonical work pages

  1. [1]

    Paz-Soldan, C

    C. Paz-Soldan, C. Chrystal, P. Lunia, A. O. Nelson, K. E. Thome, M. E. Austin, T. B. Cote, A. W. Hyatt, N. Leuthold, A. Marinoni, T. H. Osborne, M. Pharr, O. Sauter, F. Scotti, T. M. Wilks, H. S. Wilson, Si- multaneous access to high normalized density, current, pressure, and confinement in strongly-shaped di- verted negative triangularity plasmas, Nuclea...

    doi:10.1088/1741-4326/ad69a4 2024

  2. [2]

    G. D. Giannatale, A. Bottino, S. Brunner, M. Muru- gappan, L. Villard, System size scaling of triangularity effects on global temperature gradient-driven gyrokinetic simulations, Plasma Physics and Controlled Fusion 66 (9) (2024) 095003, publisher: IOP Publishing. doi:10.1088/1361-6587/ad5df9. URL https://dx.doi.org/10.1088/1361-6587/ ad5df9

    doi:10.1088/1361-6587/ad5df9 2024

  3. [3]

    Merlo, M

    G. Merlo, M. Dicorato, B. Allen, T. Dannert, K. Ger- maschewski, F. Jenko, On the e ffect of negative triangularity on ion temperature gradient turbulence in tokamaks, Physics of Plasmas 30 (10) (2023) 102302. doi:10.1063/5.0167292. URL https://pubs.aip.org/pop/ article/30/10/102302/2915113/ On-the-effect-of-negative-triangularity-on-ion

    doi:10.1063/5.0167292 2023

  4. [4]

    S. Y . Medvedev, M. Kikuchi, L. Villard, T. Takizuka, P. Diamond, H. Zushi, K. Nagasaki, X. Duan, Y . Wu, A. A. Ivanov, A. A. Martynov, Y . Y . Poshekhonov, A. Fa- soli, O. Sauter, The negative triangularity tokamak: Sta- bility limits and prospects as a fusion energy system 55 063013, publisher: Institute of Physics Publishing. doi: 10.1088/0029-5515/55/...

    doi:10.1088/0029-5515/55/6/063013

  5. [5]

    A. O. Nelson, L. Schmitz, T. Cote, J. F. Parisi, S. Stewart, C. Paz-Soldan, K. E. Thome, M. E. Austin, F. Scotti, J. L. Barr, A. Hyatt, N. Leuthold, A. Marinoni, T. Neiser, T. Osborne, N. Richner, A. S. Welander, W. P. Wehner, R. Wilcox, T. M. Wilks, J. Yang, t. D.-D. Team, Char- acterization of the ELM-free negative triangularity 10 edge on DIII-D, Plasm...

    doi:10.1088/1361-6587/ad6a83 2024

  6. [6]

    Nelson, L

    A. Nelson, L. Schmitz, C. Paz-Soldan, K. Thome, T. Cote, N. Leuthold, F. Scotti, M. Austin, A. Hyatt, T. Osborne, Robust Avoidance of Edge-Localized Modes alongside Gradient Formation in the Negative Triangularity Toka- mak Edge, Physical Review Letters 131 (19) (2023) 195101. doi:10.1103/PhysRevLett.131.195101. URL https://link.aps.org/doi/10.1103/ PhysR...

    doi:10.1103/physrevlett.131.195101 2023

  7. [7]

    A. O. Nelson, C. Paz-Soldan, S. Saarelma, Prospects for h-mode inhibition in negative tri- angularity tokamak reactor plasmas 62 096020. doi:10.1088/1741-4326/ac8064. URL https://doi.org/10.1088/1741-4326/ ac8064

    doi:10.1088/1741-4326/ac8064

  8. [8]

    Saarelma, M

    S. Saarelma, M. E. Austin, M. Knolker, A. Marinoni, C. Paz-Soldan, L. Schmitz, P. B. Snyder, Ballooning instability preventing the h-mode access in plasmas with negative triangularity shape on the DIII-d tokamak 63 (105006), ISBN: 10.1088/1361. doi:10.1088/1361. URL https://doi.org/10.1088/1361-6587/ ac1ea4

    doi:10.1088/1361

Show all 41 references
  1. [9]

    T. M. Collaboration, G. Rutherford, H. S. Wilson, A. Saltzman, D. Arnold, J. L. Ball, S. Benjamin, R. Biela- jew, N. d. Boucaud, M. Calvo-Carrera, R. Chandra, H. Choudhury, C. Cummings, L. Corsaro, N. DaSilva, R. Diab, A. R. Devitre, S. Ferry, S. J. Frank, C. J. Hansen, J. Jer...

    2024

  2. [10]

    H. S. Wilson, A. O. Nelson, J. McClenaghan, P. Rodriguez-Fernandez, J. Parisi, C. Paz-Soldan, Characterizing the negative triangularity reactor core operating space with integrated modeling, Plasma Physics and Controlled Fusion 67 (1) (2025) 015026. doi:10.1088/1361-6587/ad9be...

    2025 doi

  3. [11]

    K. E. Thome, M. E. Austin, A. Hyatt, A. Marinoni, A. O. Nelson, C. Paz-Soldan, F. Scotti, W. Boyes, L. Casali, C. Chrystal, S. Ding, X. D. Du, D. Eldon, D. Ernst, R. Hong, G. R. McKee, S. Mordijck, O. Sauter, L. Schmitz, J. L. Barr, M. G. Burke, S. Coda, T. B. Cote, M. E. Fens...

    2024

  4. [12]

    Marinoni, M

    A. Marinoni, M. Austin, A. Hyatt, S. Saarelma, F. Scotti, Z. Yan, C. Chrystal, S. Coda, F. Glass, J. Hanson, A. McLean, D. Pace, C. Paz-Soldan, C. Petty, M. Porko- lab, L. Schmitz, F. Sciortino, S. Smith, K. Thome, F. Turco, the DIII-D Team, Diverted negative triangular- ity p...

    doi

  5. [13]

    Balestri, P

    A. Balestri, P. Mantica, A. Mariani, F. Bagnato, T. Bol- zonella, J. Ball, S. Coda, M. Dunne, M. Faitsch, P. In- nocente, P. Muscente, O. Sauter, M. Vallar, E. Viezzer, t. T. Team, t. E. T. E. Team, Experiments and gyrokinetic simulations of TCV plasmas with negative triangula...

    2024 doi

  6. [14]

    Pochelon, T

    A. Pochelon, T. Goodman, M. Henderson, C. Angioni, R. Behn, S. Coda, F. Hofmann, J.-P. Hogge, N. Kirneva, A. Martynov, J.-M. Moret, Z. Pietrzyk, F. Porcelli, H. Reimerdes, J. Rommers, E. Rossi, O. Sauter, M. Tran, H. Weisen, S. Alberti, S. Barry, P. Blanchard, P. Bosshard, R. ...

  7. [15]

    Camenen, A

    Y . Camenen, A. Pochelon, R. Behn, A. Bottino, A. Bor- tolon, S. Coda, A. Karpushov, O. Sauter, G. Zhuang, Im- pact of plasma triangularity and collisionality on electron heat transport in TCV l-mode plasmas 47 (7) 510–516. doi:10.1088/0029-5515/47/7/002. URL https://doi.org/1...

    doi

  8. [16]

    Aucone, P

    L. Aucone, P. Mantica, T. Happel, J. Hobirk, T. P¨utterich, 11 B. Vanovac, C. F. B. Zimmermann, M. Bernert, T. Bol- zonella, M. Cavedon, M. Dunne, R. Fischer, P. Innocente, A. Kappatou, R. M. McDermott, A. Mariani, P. Mus- cente, U. Plank, F. Sciortino, G. Tardini, t. E. W. Te...

    2024 doi

  9. [17]

    Merle, O

    A. Merle, O. Sauter, S. Yu Medvedev, Pedestal prop- erties of h-modes with negative triangularity using the EPED-CH model 59 (10), publisher: Institute of Physics Publishing. doi:10.1088/1361-6587/aa7ac0. URL https://doi.org/10.1088/1361-6587/ aa7ac0

    doi

  10. [18]

    Nelson, C

    A. Nelson, C. Vincent, H. Anand, J. Lovell, J. Parisi, H. S. Wilson, K. Imada, W. Wehner, M. Kochan, S. Blackmore, G. McArdle, S. Guizzo, L. Rondini, S. Freiberger, C. Paz- Soldan, First access to elm-free negative triangularity at low aspect ratio, Nuclear Fusion (2024). URL ...

    2024 arXiv

  11. [19]

    Doyle, D

    S. Doyle, D. Lopez-Aires, A. Mancini, M. Agredano- Torres, J. Garcia-Sanchez, J. Segado-Fernandez, J. Ayllon-Guerola, M. Garcia-Mu ˜noz, E. Viezzer, C. Soria-Hoyo, J. Garcia-Lopez, G. Cunningham, P. Bux- ton, M. Gryaznevich, Y . Hwang, K. Chung, Magnetic equilibrium design for...

    2021

  12. [20]

    Mancini, J

    A. Mancini, J. Ayllon-Guerola, S. Doyle, M. Agredano- Torres, D. Lopez-Aires, J. Toledo-Garrido, E. Viezzer, M. Garcia-Mu ˜noz, P. Buxton, K. Chung, J. Garcia- Dominguez, J. Garcia-Lopez, M. Gryaznevich, J. Hidalgo-Salaverri, Y . Hwang, J. Segado-Fern ´andez, Mechanical and el...

    2021

  13. [21]

    Segado-Fernandez, A

    J. Segado-Fernandez, A. Mancini, J. Garcia-Dominguez, J. Ayllon-Guerola, D. Cruz-Zabala, L. Velarde, M. Garcia-Mu˜noz, E. Viezzer, C. Navarro, M. Agredano- Torres, P. Vicente-Torres, Analysis and design of the central stack for the smart tokamak, Fusion Engineer- ing and Desig...

    2023

  14. [22]

    Lehnen, K

    M. Lehnen, K. Aleynikova, P. Aleynikov, D. Camp- bell, P. Drewelow, N. Eidietis, Y . Gasparyan, R. Granetz, Y . Gribov, N. Hartmann, E. Holl- mann, V . Izzo, S. Jachmich, S.-H. Kim, M. Ko ˇcan, H. Koslowski, D. Kovalenko, U. Kruezi, A. Loarte, S. Maruyama, G. Matthews, P. Park...

    2015

  15. [23]

    A. D. Maris, A. Wang, C. Rea, R. Granetz, E. Marmar, The impact of disruptions on the eco- nomics of a tokamak power plant, Fusion Sci- ence and Technology 80 (5) (2024) 636–652. doi:10.1080/15361055.2023.2229675. URL https://doi.org/10.1080/15361055.2023. 2229675

    2024

  16. [24]

    J. Song, C. Paz-Soldan, J. Lee, Impact of negative trian- gularity plasma shaping on the n = 0 resistive wall mode in a tokamak 61 (9) 096033, publisher: IOP Publishing. doi:10.1088/1741-4326/ac189a. URL https://doi.org/10.1088/1741-4326/ ac189a

    doi

  17. [25]

    Guizzo, A

    S. Guizzo, A. O. Nelson, C. Hansen, F. Logak, C. Paz- Soldan, Assessment of vertical stability for negative triangularity pilot plants, Plasma Physics and Controlled Fusion 66 (6) (2024) 065018, publisher: IOP Publishing. doi:10.1088/1361-6587/ad4175. URL https://dx.doi.org/10...

    2024 doi

  18. [26]

    Hansen, I

    C. Hansen, I. Stewart, D. Burgess, M. Pharr, S. Guizzo, F. Logak, A. Nelson, C. Paz-Soldan, Tokamaker: An open-source time-dependent grad- shafranov tool for the design and modeling of axisymmetric fusion devices, Computer Physics Communications 298 (2024) 109111. doi:https: /...

    2024

  19. [27]

    W. A. Houlberg, S. E. Attenberger, L. M. Hively, Contour analysis of fusion reactor plasma per- formance, Nuclear Fusion 22 (7) (1982) 935. doi:10.1088/0029-5515/22/7/006. URL https://dx.doi.org/10.1088/0029-5515/ 22/7/006

    1982 doi

  20. [28]

    Kembleton, M

    R. Kembleton, M. Siccinio, F. Maviglia, F. Militello, Benefits and challenges of advanced diver- tor configurations in demo, Fusion Engineering and Design 179 (2022) 113120. doi:https: //doi.org/10.1016/j.fusengdes.2022.113120. URL https://www.sciencedirect.com/science/ articl...

    2022

  21. [29]

    Kuang, N

    A. Kuang, N. Cao, A. Creely, C. Dennett, J. Hecla, B. LaBombard, R. Tinguely, E. Tolman, H. Ho ff- man, M. Major, J. Ruiz Ruiz, D. Brunner, P. Grover, 12 C. Laughman, B. Sorbom, D. Whyte, Concep- tual design study for heat exhaust management in the arc fusion pilot plant, Fusi...

    2018 doi

  22. [30]

    A. Q. Kuang, S. Ballinger, D. Brunner, J. Canik, A. J. Creely, T. Gray, M. Greenwald, J. W. Hughes, J. Irby, B. LaBombard, et al., Divertor heat flux challenge and mitigation in sparc, Journal of Plasma Physics 86 (5) (2020) 865860505. doi:10.1017/ S0022377820001117

    2020

  23. [31]

    A. O. Nelson, A. Hyatt, W. Wehner, A. Welander, C. Paz-Soldan, T. Osborne, H. Anand, K. E. Thome, Vertical control of diii-d discharges with strong negative triangularity 65 (4). URL https://dx.doi.org/10.1088/1361-6587/ acbe65

    doi

  24. [32]

    J. P. Freidberg, A. Cerfon, J. P. Lee, Tokamak elon- gation – how much is too much? Part 1. The- ory, Journal of Plasma Physics 81 (6) 515810607. doi:10.1017/S0022377815001270. URL https://www.cambridge.org/core/product/ identifier/S0022377815001270/type/journal_ article

    doi

  25. [33]

    J. P. Lee, A. Cerfon, J. P. Freidberg, M. Greenwald, Toka- mak elongation – how much is too much? Part 2. Nu- merical results, Journal of Plasma Physics 81 (6) (2015) 515810608. doi:10.1017/S0022377815001300. URL https://www.cambridge.org/core/product/ identifier/S002237781500...

    2015 doi

  26. [34]

    Guang-Jun, W

    L. Guang-Jun, W. Bao-Nian, E ffect of passive plates on vertical instability in the EAST toka- mak, Chinese Physics B 21 (8) (2012) 085201. doi:10.1088/1674-1056/21/8/085201. URL https://dx.doi.org/10.1088/1674-1056/ 21/8/085201

    2012 doi

  27. [35]

    G. Lee, M. Kwon, C. Doh, B. Hong, K. Kim, M. Cho, W. Namkung, C. Chang, Y . Kim, J. Kim, H. Jhang, D. Lee, K.-I. You, J. Han, M. Kyum, J.-W. Choi, J. Hong, w. c. Kim, B.-S. Kim, K. Team, Design and construction of the kstar tokamak, Nuclear Fusion 41 (05 2002). doi:10.1088/002...

    2002 doi

  28. [36]

    Sehmer, K

    T. Sehmer, K. Lackner, E. Strumberger, E. Fable, O. Kar- daun, P. McCarthy, A. U. Team, Growth of axisymmetric instabilities in asdex upgrade, Fusion Science and Tech- nology 70 (1) (2016) 73–82.arXiv:https://doi.org/ 10.13182/FST15-175, doi:10.13182/FST15-175. URL https://doi...

    2016 doi

  29. [37]

    V . D. Pustovitov, Models and scalings for the disruption forces in tokamaks, Nuclear Fusion 62 (2) (2022) 026036, publisher: IOP Publishing. doi:10.1088/1741-4326/ac3fe9. URL https://dx.doi.org/10.1088/1741-4326/ ac3fe9

    2022 doi

  30. [38]

    N. W. Eidietis, S. P. Gerhardt, R. S. Granetz, Y . Kawano, M. Lehnen, J. B. Lister, G. Pautasso, V . Riccardo, R. L. Tanna, A. J. Thornton, T. I. D. D. Partici- pants, The ITPA disruption database, Nuclear Fusion 55 (6) (2015) 063030, publisher: IOP Publishing. doi:10.1088/002...

    2015 doi

  31. [39]

    A. J. Creely, M. J. Greenwald, S. B. Ballinger, D. Brunner, J. Canik, J. Doody, T. F ¨ul¨op, D. T. Garnier, R. Granetz, T. K. Gray, et al., Overview of the sparc tokamak, Journal of Plasma Physics 86 (5) (2020) 865860502. doi:10. 1017/S0022377820001257

    2020

  32. [40]

    B. N. Sorbom, J. Ball, T. R. Palmer, F. J. Mangia- rotti, J. M. Sierchio, P. Bonoli, C. Kasten, D. A. Sutherland, H. S. Barnard, C. B. Haakonsen, J. Goh, C. Sung, D. G. Whyte, ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demoun...

    2015 doi

  33. [41]

    Hansen, A

    C. Hansen, A. Battey, A. Braun, S. Miller, M. Lagieski, I. Stewart, R. Sweeney, C. Paz-Soldan, Thincurr: An open-source 3d thin-wall eddy current modeling code for the analysis of large-scale systems of conducting struc- tures (2024). URL https://arxiv.org/abs/2412.14962 13

    2024 arXiv

Pith tools

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