| Date / Time (ET) | Speaker | Title of Talk (PDF Link) |
|---|---|---|
| 2025-02-06 12:00pm-1:00pm | TBA | TBA |
| 2025-01-23 12:00pm-1:00pm | K. Garcia | Resilient Stellarator Divertor Characteristics in the Helically Symmetric eXperiment Abstract: Resilient divertor features connected to open chaotic edge structures in the Helically Symmetric Experiment (HSX) are investigated. For the first time, an expanded vessel wall was considered that would give space for implementation of a physical divertor target structure. The analysis was done for four different magnetic configurations with very different chaotic plasma edges. A resilient plasma wall interaction pattern was identified across all configurations. This manifests as qualitatively very similar footprint behavior across the different plasma equilibria. Overall, the resilient field lines of interest with high connection length LC lie within a helical band along the wall for all configurations. This resiliency can be used to identify the best location of a divertor. The details of the magnetic footprint's resilient helical band is subject to specific field line structures which are linked to the penetration depth of field lines into the plasma and directly influence the heat and particle flux patterns. The differences arising from these details are characterized by introducing a new metric, the minimum radial connection min(δN) of a field line from the last closed flux surface. The relationship, namely the deviation from a scaling law, between min(δN) and LC of the field lines in the plasma edge field line behavior suggests that the field lines are associated with structures such as resonant islands, cantori, and turnstiles. This helps determine the relevant magnetic flux channels based on the radial location of these chaotic edge structures and the divertor target footprint. These details will need to be taken into account for resilient divertor design. (Video Recording of Talk) |
| 2024-12-12 12:00pm-1:00pm | C. Moreno | Numerical Design Optimization of Fusion Stellarator Breeding Blanket and Shielding Systems for Neutronics Performance Abstract: Spurred by recent advancements in supporting technologies, government support, and the privatization of fusion power, fusion stellarators have experienced a renewed research and development effort. Stellarator development is multifaceted, but one critical area of development focuses on in-vessel components. The engineering design of in-vessel components for stellarator fusion power plants can be cumbersome, challenging, and complex. Characterized by many degrees of freedom, the design space for such components is too broad to be effectively explored using conventional means. To more efficiently iterate through the design space and achieve an optimal design, autonomous, numerical design optimization methods can be employed. The goal of this proposed work is to establish an efficient design workflow that results in an optimized conceptual design, leveraging modern computational hardware and software. (Video Recording of Talk) |
| 2024-11-14 12:00pm-1:00pm | Various | General Discussions |
| 2024-10-17 12:00pm-1:00pm | S. Buller | Optimization of Compact Quasi-Axisymmetric Stellarators With Varying Profiles Abstract: TBSL |
| 2024-10-03 12:00pm-1:00pm | Y. Elmacioglu | The Stellarator Database Abstract: Due to their complex 3D shapes, numerical simulations of Stellarators require significantly longer runtimes compared to axisymmetric toroidal devices, Tokamaks. Moreover, the lack of experimental facilities makes collecting data harder. As a result, the Stellarator community cannot take advantage of the machine learning models, which have proven effective in Tokamak research. Our work on a stellarator database tries to solve the issue of access to data of stellarator numerical simulations obtained from codes such as VMEC, DESC, and SIMSOPT. As a first phase, we completed the DESC part of the database which gives users the ability to make queries on existing data, download output files and upload simulation results to the database through the Python interface. The website for the database can be accessed from https://ye2698.mycpanel.princeton.edu/. (Video Recording of Talk) |
| 2024-09-19 12:00pm-1:00pm | Sanket Patil | Preconditioning and Validation of NIMSTELL for Linear MHD and its Application to Quasisymmetric Configurations* Abstract: MHD modeling of stellarators is a numerically challenging and computationally expensive problem due to non-axisymmetric geometry and equilibrium. Improving the efficiency of such calculations in NIMSTELL was crucial for making calculations in complex optimized configurations computationally tractable. Since non-consecutive Fourier components of perturbed fields are coupled in multi-field-period stellarators, preconditioning with user-defined sets of Fourier harmonics was implemented. This reduces the CPU time by a factor of the number of field periods squared. Additionally, since the sparse matrix structure is determined solely by the 2D mesh and not the Fourier harmonics, a reduced matrix is used to minimize the memory required by ParMETIS[1] for calculating a fill-reducing permutation. NIMSTELL was benchmarked against JOREK and CASTOR3D for tearing and ballooning in a set of W7-A cases[2]. NIMSTELL and CASTOR3D growth rates agree with a maximum deviation of 1.5% for tearing and 5.8% for ballooning modes. A configuration based on “new QA”[3] was developed to admit a (2, 1) tearing mode by artificially specifying the rotational transform. Resistivity scan shows a much slower scaling of the growth rate than the 3/5th power, possibly due to wall proximity. A 2.5% beta QH configuration[4] is shown to develop resistive interchange in the region where rotational transform is close to unity. The growth rate normalized by the Alfven time is approximately 5%. References: [1] G. Karypis, Ency. Parallel Comput., 1117–1124 (2011). [2] N. Nikulsin, et al., Phys. Plasmas 29, 063901 (2022). [3] M. Landreman and E. Paul, Phys. Rev. Lett. 128, 035001 (2022). [4] M. Landreman, et al., Phys. Plasmas 29, 082501 (2022). *Work supported by US DOE grants DE-SC0024548 and DE-FG02-99ER54546. (Video Recording of Talk) |
| 2024-08-22 12:00pm-1:00pm | A. Boozer | Method for Improving Magnetic Field Coils Abstract: A central issue in the design of tokamaks or stellarators is the coils that produce the external magnetic fields. The freedom that remains unstudied in the design of coils is enormous. This freedom could be quickly studied computationally at low cost with high reliability. In particular, the space between toroidal field or modular coils that block access to the plasma chamber could be increased by a large factor. The concept of current-potential patches, which was developed in Todd Elder’s thesis, provides a method for separating the study of the feasibility of coils with attractive physics properties from the engineering design of specific coils. (Video Recording of Talk) |
| 2024-06-27 12:00pm-1:00pm | V. Badalassi | Blanket Analysis & Design Using Modeling and Simulation Abstract: The blanket is a complex and fundamental component for future fusion power reactors, yet none has been built and tested; the current TRL level of one of the most studied blanket concepts (the Dual Coolant Lead Lithium Blanket, quite popular in DOE FES) is only two. Despite this, all the fusion startups want to pick a blanket concept and design it in detail. In this presentation, I will show how modelling and simulation, particularly the Fusion Energy Reactor Models Integrator (FERMI) simulation framework, may reduce the risk of deploying technology from such a low technology readiness, and I will present a new blanket concept. FERMI is an integrated simulation environment under development for the coupled simulation of the plasma, first wall, and blanket of fusion reactor designs. The FERMI's original goals are to shorten the overall design cycle while guaranteeing unprecedented accuracy, thus integrating fusion design activities, facilitating an optimal reactor design, and reducing development risks. These goals are achieved by coupling single-physics solvers into a multi-physics simulation environment (FERMI). The Integrated Plasma Simulator (IPS)–FASt TRANsport (IPS-FASTRAN) simulation framework is used for the following: plasma physics, MCNP/Shift codes for neutron and photon transport, OpenFoam for computational fluid dynamics and magnetohydrodynamics (MHD), HyPerComp Incompressible MHD solver for Arbitrary Geometry (HIMAG) for dual-coolant lead-lithium (DCLL) blankets, and DIABLO for structural mechanics simulations. These codes are coupled using the open-source library named precise Code Interaction Coupling Environment (preCICE). FERMI’s features are tested with the analysis of the liquid immersion blanket (LIB) [proposed in the Affordable Robust Compact (ARC)–class tokamak design], the DCLL blanket [proposed in the Fusion Pilot Plant (FPP) design], and other benchmark cases. The calculated figures of merit are the tritium breeding ratio, material activation, displacements per atom, shutdown dose rate, heat deposited in the vacuum vessel and blanket, temperature hot spots, and displacements caused by swelling and creep. A critical technical problem is multi-physics code coupling, which is tackled here, and the first three-dimensional (3D) simulations of the DCLL-FPP and LIB-ARC blankets are presented. FERMI represents the first effort to perform 3D simulations of nuclear fusion first wall and blankets in a fully coupled multi-physics manner, and it shows the way to de-risk the detailed design of blankets. Finally, I will present the patent pending “Nested Pebble Bed Blanket”, a revolutionary blanket concept that may solve most issues affecting existing blankets concepts. (Video Recording of Talk) |
| 2024-06-13 12:00pm-1:00pm | W. Sengupta | Periodic Korteweg-de Vries Soliton Potentials Generate Magnetic Field Strength with Excellent Quasisymmetry Abstract: Quasisymmetry (QS) is a hidden symmetry of the magnetic field strength, |B|, that con- fines charged particles effectively in a three-dimensional toroidal plasma equilibrium. Here, we show that QS has a deep connection to the underlying symmetry that makes solitons possible. Our approach uncovers a hidden lower dimensionality of |B| on a magnetic flux sur- face, which could make stellarator optimization schemes significantly more efficient. Recent numerical breakthroughs (M. Landreman and E. Paul, Phys. Rev. Lett. 128, 035001 (2022)) have yielded configurations with excellent volumetric QS and surprisingly low magnetic shear. Our approach elucidates why the magnetic shear is low in these configurations. Furthermore, we deduce an upper bound on the maximum toroidal volume that can be quasisymmetric and verify it for the Landreman-Paul precise quasiaxisymmetric (QA) stellarator configuration. In the neighborhood of the outermost surface, we show that the |B| approaches the form of the 1-soliton reflectionless potential (I. Gjaja and A. Bhattacharjee, Phys. Rev. Lett. 68, 2413 (1992)). We present three independent approaches to demonstrate that quasisymmetric |B| is described by well-known integrable systems such as the Korteweg-de Vries (KdV) equation. The first approach is weakly nonlinear multiscale perturbation theory, which highlights the crucial role that magnetic shear plays in QS. We show that the overdetermined problem of finding quasisymmetric vacuum fields admits solutions for which the rotational transform is not free but highly constrained. We obtain the KdV equation (and, more specifically, Gard- ner’s equation for certain choices of parameters). Our second approach is non-perturbative and based on ensuring single-valuedness of |B|, which directly leads to its Painlevé property shared by the KdV equation. Our third approach uses machine learning, trained on a large dataset of numerically optimized quasisymmetric stellarators. We robustly recover the KdV (and Gardner’s) equation from the data. (Video Recording of Talk) |
| 2024-03-11 1:00pm-2:00pm | H. Zhu | Zonal Flows in Stellarators Abstract: (Video Recording of Talk) |
| 2024-03-07 12:00pm-1:00pm | F. Fu | Fast Global Stellarator Coil Optimization with Quadratic Objectives Abstract: Most present stellarator designs are produced by costly two-stage optimization: the first for an optimized equilibrium, and the second for a coil design reproducing its magnetic configuration. Few proxies for coil complexity and force exists at the equilibrium stage. Rapid initial state finding for both stages is a field of active research. Most present fast coil optimization codes use the least square current potential method by Merkel (NESCOIL) [1], with recent improvement in regularization by Landreman (REGCOIL)[2] and Boozer[3]. While elegant, the method is limited to modeling the norms of linear functions in coil current. We present QUADCOIL, a fast, global coil optimization method that targets combinations of linear and quadratic functions of the current. It can directly constrain and/or minimize a wide range of physics unavailable in NESCOIL and REGCOIL, including stored magnetic energy, Lorentz force [4], curvature, and field-current alignment. QUADCOIL requires no initial guess, finds the global optima in the design space, and runs in core-seconds. It supports most regularization techniques developed for NESCOIL and REGCOIL. We demonstrate agreement between QUADCOIL and local optimization using a prototype using cvxpy[5] and MOSEK as optimizer. For a given equilibrium and winding surface, QUADCOIL can rapidly estimate the best achievable value for engineering metrics. It can also provide improved initial guesses for high-fidelity coil optimization. (Video recording of talk) |
| 2024-02-08 12:00pm-1:00pm | R. Ramasamy | Nonlinear MHD Studies of Soft Beta Limits in W7-AS Abstract: Nonlinear MHD simulation studies are presented towards understanding the underlying mechanism behind experimentally observed soft beta limits in W7-AS. First, linear benchmarks of a (2, 1) tearing mode in W7-AS geometry, and interchange modes in a finite beta, net-zero current carrying stellarator with low magnetic shear are used to demonstrate the capabilities of a recently derived reduced nonlinear MHD model. A validation study is then conducted on experimental reconstructions of finite beta W7-AS discharges. In agreement with past experimental and computational analysis, it is shown that (i) the MHD activity is resistive, (ii) a soft beta limit is observed, when the plasma resistivity approaches the estimated experimental value, and (iii) low n MHD activity is observed at intermediate beta values. The soft beta limit is a result of the mild saturated MHD activity, such that the plasma volume remains separated into distinct sub-volumes in which field lines are ergodically confined. The limitations in the current modeling are described, alongside an outlook for characterising soft beta limits in more detail in future work. (Video recording of talk) |
| 2024-01-11 12:00pm-1:00pm | W. Sengupta & N. Nikulsin | Asymptotic Grad-Shafranov Equations For Large Aspect Ratio High-Beta Quasisymmetric Stellarators Abstract: We study approximate quasisymmetric MHD equilibria with finite plasma beta by expanding the magnetic field of a quasisymmetric stellarator around a vacuum field, assuming the ratio of the gradients parallel and perpendicular to the vacuum field to be small. We first expand around an axisymmetric vacuum field, which results in Freidberg's high-beta stellarator (HBS) model with quasisymmetry. We derive an elliptic Grad-Shafranov equation for three-dimensional equilibria, resolving the overdetermination problem while retaining considerable freedom in flux surface-shaping. We demonstrate that quasi-axisymmetric stellarator solutions can be obtained from a tokamak by simply applying a toroidally varying vertical shift to each poloidal plane. We also discuss linear ballooning stability for the near-axisymmetric case. We then consider the more general case and show that in contrast to the quasi-axisymmetric HBS model, the overdetermination problem can still be resolved but with constraints on flux-surface shaping. Nevertheless, we can still find classes of special solutions far from axisymmetry that satisfy the overdetermined system of equations. The most prominent class is equilibria with rotating elliptical cross-sections, but we will also present other classes of solutions. (Video recording of talk) |
| 2023-11-17 11:00am-12:00 EST | A. Coelho | Global Fluid Simulations of Plasma Turbulence in Stellarators (pptx version with embedded video) Abstract: We present the first 3D, global, two-fluid, flux-driven simulations of plasma turbulence in stellarators with different configurations: one with an island divertor; another one corresponding to the TJ-K stellarator; and a set of equilibria with increasing torsion and ellipticity. The simulations were carried out with the GBS code [1], which solves the two-fluid drift-reduced Braginskii equations. The vacuum magnetic field of the island divertor configuration corresponds to a 5-field period stellarator and was constructed using the Dommaschk potentials [2]. It was found that the radial particle and heat transport is mainly driven by a field-aligned mode with low poloidal wavenumber, whose origin is investigated theoretically [3]. Transport is observed to be larger on the high-field side of the device and this is explained by means of a non-local linear theory. In contrast to tokamak simulations and experiments, but in agreement with edge measurements in W7-X [4], radial propagation of coherent filamentary structures (blobs) is not observed, revealing important differences between stellarator and tokamak edge transport mechanisms. We further present the first validation of a simulation of plasma turbulence in a stellarator configuration against experimental measurements in the TJ-K stellarator [5]. The comparison shows that GBS retrieves the main turbulence properties observed in the device, namely the fact that transport is dominated by fluctuations with low poloidal mode number. Finally we present simulations in a set of equilibria with increasing ellipticitiy and increasing torsion generated by VMEC. The limit of zero ellipticity and zero torsion corresponds to a tokamak with circular flux surfaces, allowing to study edge turbulence in the transition between a tokamak and a stellarator. The role of ellipticity and torsion as well as of magnetic shear is discussed. (Video recording of talk) |
| 2023-11-15 11:00am-12:00 EST | S. Buller | Impurity Transport In Stellarators With Implications For Stellarator Optimization Abstract: The stellarator concept relies on careful optimization to confine trapped particle orbits. The two main approaches for confining particles in stellarators is to either optimize for quasi-symmetry or quasi-isodynamicity. The different approaches result in very different collisional impurity transport, and may require different strategies for avoiding accumulation of heavy impurities in reactor scenarios. Quasi-isodynamic configurations, as a result of having very low parallel current, have very low collisional impurity transport. Therefore, such configurations likely have to rely on turbulence to flush out the impurities. We may thus expect quasi-isodynamic configurations optimized for low turbulent transport to be especially susceptible to accumulation of heavy impurities like tungsten. In this talk, we'll review the theory of impurity transport in stellarators, and with an eye towards potential strategies for avoiding impurity accumulation based on what we know and what we don't know. (Video recording of talk) |