聚变科学与工程资源库
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Energetic particle driven Alfvén eigenmodes and associated energetic particle redistribution in a tokamak burning plasma
Nuclear FusionAbstract Energetic-particle driven Alfvén eigenmodes (AEs) and associated redistribution of energetic particles in phase space are investigated using kinetic-magnetohydrodynamic (MHD) hybrid simulations for a tokamak burning plasma with weakly reversed magn…
MHD, disruptions and control physics: Chapter 4 of the special issue: on the path to tokamak burning plasma operation
Nuclear FusionAbstract In this chapter, we review the progress in MHD stability, disruptions and control in magnetic fusion research that has occurred over the past (more than) one and a half decades since the publication by Hender et al in 2007 on the same topic as part…
Neural network-based classification and regression of magnetohydrodynamic modes in tokamaks
Nuclear FusionAbstract We present a machine learning-based magnetohydrodynamic (MHD) classifier and regressor that utilizes real or complex-valued 3D magnetic sensor array data to determine neoclassical tearing mode (NTM) onset times in tokamaks with millisecond accuracy…
Variability of MHD instabilities in benign termination of high-current runaway electron beams in the JET and DIII-D tokamaks
Nuclear FusionAbstract Benign termination, in which magnetohydrodynamic (MHD) instabilities deconfine runaway electrons (REs) following hydrogenic injections, is a promising strategy for mitigating dangerous RE loads after disruptions. Recent experiments on the Joint Eur…
Hybrid kinetic-MHD modeling of alpha-driven TAEs in the SPARC tokamak
Nuclear FusionAbstract As the magnetic confinement fusion community prepares for the next generation of fusion devices and burning plasmas, there is still a question of whether fast ions (FIs) will drive MHD instabilities, causing significant redistribution or even loss…
Disruption mitigation modeling for the SPARC tokamak
Physics of PlasmasTwo primary systems planned for disruption mitigation in the SPARC tokamak, massive gas injection (MGI), and the runaway electron mitigation coil (REMC), are modeled with the 3D MHD code NIMROD. MGI is modeled in four configurations, and each of the 6-valve…
Gyrokinetic transport driven by ubiquitous modes in LTX-like tokamak with ‘flat’ temperature
Nuclear FusionAbstract A global, gyro-kinetic nonlinear study of the ubiquitous mode (UM) for Lithium Tokamak eXperiment (LTX)-like profiles, under flat electron and ion temperature scenarios is conducted using a global gyrokinetic model. Exact MHD equilibria with circul…
The properties of resistive MHD modes and unstable spectra in advanced tokamak regimes
arXivAbstract Advanced tokamak regimes, featuring extended regions of low magnetic shear, are promising candidates for future fusion reactors but are also more prone to specific kinds of MHD instabilities. The proximity to a rational surface in a very low shear…
A quasi-isodynamic stellarator configuration towards a fusion power plant
Journal of Plasma PhysicsThis work demonstrates that magnetohydrodynamic (MHD) stable, quasi-isodynamic (QI) stellarator equilibria with reduced turbulence can be generated with an optimised coilset. We present one such equilibrium which, when being generated by coils, maintains th…
Coupled 2D MHD and runaway electron fluid simulations of SPARC disruptions
Physics of PlasmasRunaway electrons (REs) generated during disruption events in tokamaks can carry mega-Ampère level currents, potentially causing damage to plasma-facing components. Understanding RE evolution during disruption events is important for evaluating strategies t…
Gyrokinetic simulations of magnetohydrodynamic modes in stellarator plasmas
Journal of Plasma PhysicsAbstract For small-shear helical-axis stellarators, linear ideal-magnetohydrodynamic (MHD) stability calculations and full-torus, nonlinear, electromagnetic gyrokinetic (GK) simulations (the latter with this unprecedented combination of objectives in stella…
Sawtooth crash in tokamak as a sequence of Multi-region Relaxed MHD equilibria
arXivThis study examines the sawtooth crash phenomenon in tokamak plasmas by modelling it as a sequence of Multi-region Relaxed Magnetohydrodynamic (MRxMHD) equilibria. Using the Stepped-Pressure Equilibrium Code (SPEC), we constructed a series of equilibria rep…
仿星器阿尔法粒子约束贝叶斯优化数据
Stellarator Optimization Research Team包含仿星器MHD平衡、优化软件输出以及论文图表生成数据与脚本，用于研究数据驱动参数空间和降维方法下的阿尔法粒子约束优化。
KARHU边界区MHD稳定性代理模型
DigiFusion面向理想剥离-气球模MHD稳定性分析的机器学习代理模型，用于近似MISHKA稳定性计算，并提供DIII-D、JET及跨装置模型权重。
JOREK 非线性MHD代码
JOREK Team用于托卡马克非线性MHD现象研究的代码、出版物和项目资料入口。
Open FUSION Toolkit
Open FUSION Toolkit Team面向等离子体与聚变工程二维/三维问题的有限元工具集，包含平衡、薄壁电磁和扩展MHD等求解组件。
DESC仿星器平衡与优化套件
PlasmaControl面向三维磁流体平衡求解与仿星器优化的开源软件，采用伪谱方法和自动微分支持平衡计算、目标函数优化及设计研究。
Achievement of a high-density, high-confinement, and high-beta tokamak plasma regime in DIII-D, and implications for a lower-current path for ITER and FPP
IOP PublishingExperiments on DIII-D have demonstrated a density-confinement synergy that enables sustainment of high performance in a previously unattained parameter regime of simultaneous very high energy confinement quality (H<sub>98y2</sub> ≥ 1.5), very high line-average density Greenwald fraction (ƒ<sub>Gr</sub> = πa<sup>2</sup>< n >/I<sub>P</sub> ≥ 1.4), and high toroidal beta (β<sub>T</sub> ≥ 3%). Tokamak operation in this regime is essential for a compact steady-state FPP, as well as for Q=10 with 500 MW of fusion power in ITER at I<sub>P</sub> << 15 MA. These experiments leveraged the knowledge that, in the high-poloidal-beta (β<sub>P</sub>) regime, impurity and density gradients can enhance turbulence stabilization caused by high α<sub>MHD</sub> (α<sub>MHD</sub>~(dβ<sub>P</sub>)⁄dr). This was described by theoretical predictions and gyrokinetic transport simulations [M.T. Kotschenreuther et al, 2024 Nucl. Fusion, 64 076033], and later confirmed by experiments on DIII-D [S. Ding et al, 2024 Nature 629 555]. To increase both β<sub>P</sub> and β<sub>T</sub>, the new experiments increased the ideal-wall stability β<sub>N</sub>-limit by using a smaller plasma-outer wall distance and higher triangularity in the plasma cross section (top/bottom average δ~0.9), enabled by the recent “shape & volume rise” (SVR) modification to the DIII-D divertor. The higher triangularity also contributed to achieving higher ƒ<sub>Gr</sub> by enabling higher pedestal density. At high density, the pedestal is ballooning limited and exhibits small and frequent ELMs, while the divertor is near detachment even without any impurity seeding. High plasma performance was attained and sustained reproducibly, with the eventual terminations brought about by an MHD mode destabilized as the current profile slowly continued to evolve. A path to stationary fully noninductive operation might include ECH injection to reduce both core impurity accumulation and the electron collisionality, thus increasing the bootstrap current. These experiments provide the first experimental demonstration of the ƒ<sub>Gr</sub>, H<sub>98y2</sub>, and β<sub>T</sub> values required simultaneously for ITER Q = 10 at I<sub>P</sub> < 10 MA, pointing to practical ways to improve the energy confinement in a fusion reactor.
Recent advances in plasma control and physics research in the Large Helical Device
IOP Science - IAEAThe Large Helical Device (LHD), the largest superconducting helical system in the world, is equipped with advanced heating and diagnostic tools, facilitating plasma control and physics research. Data assimilation was employed for electron temperature control using a real-time Thomson scattering system and real time prediction code. A virtual LHD environment enabled visualization of escaping high-energy tritium ions and demonstrated that these ions impact the rear side of the divertor plate. Pioneering results crucial to plasma control have also been achieved. Real-time wall conditioning using Lithium granule dropping improved bulk ion energy and particle transport while simultaneously enhancing the heavy impurity transport. Progress has also been made in the investigation of turbulence-driven transport. At the confinement bifurcation, ion-scale turbulence decreased, while electron-scale turbulence increased. A change in the anisotropy of turbulent eddies was also observed at the confinement bifurcation. Coexistence of local and non-local turbulence was identified in electron-scale turbulence. Non-local turbulence exhibited the rapid spatial propagation of perturbations throughout the plasma, while local turbulence followed the temperature gradient. A transition between drift-wave turbulence and magnetohydrodynamics (MHD) turbulence was observed with the turbulence minimized at the transition condition. Machine learning analysis was employed to evaluate the temperate and density conditions of this turbulence transition. Then, real-time control of fueling and heating was applied to maintain the turbulence transition condition, improving the energy confinement enhancement factor by 20%. In addition, evidence was obtained for collisionless ion heating by energetic-ion-driven geodesic acoustic modes and MHD bursts. These achievements represent unique contributions to the development of fusion reactors.
Advances in 3D transient plasma dynamics and control through MHD and hybrid fluid-kinetic simulations with JOREK
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29syliu/cuGMEC
29syliuA High-Performance Code for Gyrokinetic-MHD Hybrid Simulation on GPUs with CUDA C++