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工程图纸SVG / PNG / PDFParamak托卡马克剖切工程视图
Paramak / Fusion Energy基于Paramak开放示例生成的180度托卡马克剖切视图，呈现等离子体、包层、第一壁、偏滤器和磁体系统的空间关系。
工程图纸HTML / Engineering IllustrationsITER装置系统工程图集
ITER OrganizationITER官方装置入口，汇集托卡马克剖面、真空室、超导磁体、包层、偏滤器及低温恒温器等系统结构图。
工程图纸HTML / DiagramsITER偏滤器结构与工程图
ITER OrganizationITER官方偏滤器资料，展示偏滤器在装置中的位置、盒体组件、面向等离子体部件及高热流设计背景。
三维模型STEP / STL / GLBParamak托卡马克三维参考模型
Paramak / Fusion Energy基于Paramak开放示例生成的托卡马克三维参考模型，采用半装置剖切方式展示磁体、包层、第一壁、偏滤器与等离子体区域。
三维模型STL / STEPWendelstein 7-X简化CAD模型
Max Planck Institute for Plasma PhysicsW7-X线圈和基础装置模块的简化CAD模型，包含等离子体、偏滤器靶板、真空室、线圈及支撑结构等部件。
Design and conceptual modeling of a tokamak-like X-point divertor for the Helios quasi-axisymmetric stellarator
Fusion Engineering and DesignA novel divertor solution is presented for a pre-conceptual design point of the quasi-axisymmetric stellarator power plant, “Helios.” This solution, isomorphic to the poloidal divertor in a tokamak, features a toroidally-continuous n=0, m=2 double null conf…
Gyrokinetic Simulations for Spherical Tokamak Divertor Design
arXiv (Cornell University)Nuclear fusion is an attractive source of energy because the fuel is abundant and it produces low levels of carbon emissions. The tokamak, which confines a plasma using magnetic fields, is the most mature nuclear fusion reactor concept. Maximizing energy co…
Tokamak level performance in the optimized stellarator Wendelstein 7-X with stable peaked density profiles
Physical review. EProgress towards achieving net gain from nuclear fusion is typically characterized by the triple product n T τ . Although stellarators have several benefits for a reactor, such as the inherent steady-state capability and the lack of disruptions, the maximum…
STORM: Scrape-off layer turbulence in tokamak fusion reactors
Computer Physics CommunicationsThe scrape-off layer of a tokamak fusion reactor carries the plasma exhaust from the hot core plasma to the material surfaces of the reactor vessel. The heat loads imposed by the exhaust are a critical limit on the performance of fusion power plants. Turbul…
Scrape-off layer and divertor physics: Chapter 5 of the special issue: on the path to tokamak burning plasma operation
Nuclear FusionAbstract Since the publication of the review Progress in the ITER Physics Basis (PIPB) in 2007, significant progress has been made in understanding the processes at the plasma-material interface. This review, part of the ITPA Nuclear Fusion Special Issue On…
Extending the gyrokinetic code GENE-X to stellarators
Computer Physics CommunicationsPlasma turbulence is a fundamental process and a key transport mechanism in magnetic confinement fusion (MCF). Due to its complex, non-linear dynamics, turbulence is typically studied through numerical simulations. While turbulence in the confined core plas…
PLASMA CONTROL IN A TOKAMAK-MACHINE USING ONLY MAGNETIC MEASUREMENTS
Journal of Deep Insights in Fundamental PhysicsThe "clean" nuclear energy of tomorrow will probably be produced using Tokamak-type machines, despite the technological difficulties. Thermonuclear fusion based on the Tokamak process is more promising than that based on other types of fusion machines such…
Design specifications for the ion cyclotron heating amplifier system in the Divertor Tokamak Test facility
Fusion Engineering and DesignThis paper provides an overview of the basis of design of the high-power amplification for the Ion Cyclotron Heating system of the Divertor Tokamak Test facility. Notably, this system will be entirely based, for the first time, on solid-state technology, ma…
Stellaris: A high-field quasi-isodynamic stellarator for a prototypical fusion power plant
Fusion Engineering and DesignMagnetic confinement fusion research has so far prioritized the tokamak concept, which presents greater design simplicity at the cost of control complexity in comparison to stellarators. Recent progress on high-temperature superconductors (HTS) has enabled…
Design of an X-point slot closed divertor for the HL-3 tokamak with SOLPS-ITER
Nuclear FusionAbstract In this paper, we introduce a novel X-point Slot Closure (XSC) divertor developed for the HL-3 tokamak. The XSC divertor combines the benefits of W-shaped, V-shaped, Small Angle Slot, and Compact Radiative Divertor divertors into a compact design t…
Overview of the Helios Design: A Practical Planar Coil Stellarator Fusion Power Plant
arXiv (Cornell University)Thea Energy, Inc. has developed the preconceptual design for "Helios," a fusion power plant based on the planar coil stellarator architecture. In this overview paper, the design is summarized and the reader is referred to the other papers for more detail. T…
Diagnostics: Chapter 8 of the special issue: on the path to tokamak burning plasma operation
Nuclear FusionAbstract This chapter presents the activity conducted by the ITPA topical group (TG) on Diagnostics over about the last 15 years. Following a general introduction of the ITER Diagnostics led by their measurement roles, the document is organized in several s…
The Divertor Tokamak Test facility research plan
Nuclear FusionAbstract The Divertor Tokamak Test facility (DTT) is a device presently under construction at the ENEA site in Frascati (Italy) in the framework of a joint public/private partnership. It has been designed as a superconducting tokamak with breakeven class pe…
Investigating the influence of divertor baffles on nitrogen-seeded detachment in TCV with SOLPS-ITER simulations and TCV experiments
Nuclear FusionAbstract Plasma edge simulations with the SOLPS-ITER code are performed to study the influence of divertor baffles on nitrogen-seeded detachment in Tokamak à Configuration Variable (TCV) single-null, L-mode discharges. Scans of nitrogen seeding rate are con…
STAR_Lite: A stellarator designed to experimentally validate non-resonant divertors
arXivThe non-resonant divertor (NRD) offers a promising exhaust solution for stellarators, combining topological simplicity with resilience to magnetic field perturbations. To experimentally validate the robustness of non-resonant divertors in a quasi-axisymmetr…
Piecewise omnigenous magnetohydrodynamic equilibria as fusion reactor candidates
arXivIn piecewise omnigenous magnetic fields, charged particles remain perfectly confined in the abscence of collisions and turbulence. This concept extends the traditional notion of omnigenity, the theoretical principle upon which most of existing magnetic fusi…
Correlation between radiated power and target heat flux in the island divertor of W7-X
Nuclear FusionAbstract Radiative losses from the plasma represent a key component of global power balance in a magnetic confinement fusion device. Measurements of the plasma radiation and its spatial distribution are essential for physical studies and to ensure safe mach…
CIEMAT-QI4X: a reactor-relevant quasi-isodynamic stellarator configuration compatible with an island divertor
arXivA four-field-period quasi-isodynamic stellarator configuration is presented that exhibits small neoclassical and electrostatic turbulent transport, good fast-ion confinement over a wide range of $β$ values, small bootstrap current and an edge island structu…
Surrogate models for particle and power exhaust in divertor tokamak simulations
JuSER (Forschungszentrum Jülich)The heat exhaust constitutes one of the most critical operational limits in tokamak fusion reactors. Unmitigated, the expected heat fluxes in future reactors will exceed what is sustainable for known materials. The scrape-off layer connects the plasma and r…