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技术文档在线预览

On the role of ion temperature gradient turbulence in driving ion thermal transport in neutral beam injection-heated L-mode plasmas in a superconducting tokamak

Nuclear Fusion

Abstract In this paper, we report a detailed experimental study of the role of ion-temperature-gradient driven turbulence in driving ion thermal transport in neutral beam injection (NBI)-heated L-mode plasmas in Experimental Advanced Superconducting Tokamak…

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GRILLIX as unified fluid turbulence code for tokamaks and stellarators

Computer Physics Communications

The Flux-Coordinate Independent (FCI) approach in the edge fluid turbulence code GRILLIX has proven very successful for tokamaks in handling anisotropic turbulent structures in complex diverted geometries. We extend GRILLIX to non-axisymmetric geometries, m…

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Saturation of stimulated Raman side-scattering in inertial confinement fusion plasmas with a suprathermal electron tail

Physics of Plasmas

It is shown that the hot electrons generated by the stimulated Raman side-scattering (SRSS) can be gradually accelerated to high energies with the increase in linear density in plasmas. Meanwhile, the electron energy spectrum is strongly modified to the bi-…

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Tuning of the current drive in tokamaks with phase-shifted beating waves

AIP Advances

Recent advancements in tokamak devices have allowed for reaching very high plasma temperatures, giving hope for the production of thermonuclear fusion power. The theory of the generation of the electromotive force (EMF) and current drive in plasma through i…

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On the shielding of the tokamak coolant systems in the EU-DEMO

Nuclear Fusion

Abstract The conceptual development of the EUropean DEMOnstration fusion reactor (EU-DEMO) envisages a series of modifications aimed at improving the design of the reactor and its plant systems and triggering iterative calculation procedures for an organic…

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Tessellation-based analysis of impurity clustering in the edge plasma of tokamaks

Journal of Plasma Physics

Confinement quality in fusion plasma is influenced significantly by the presence of heavy impurities, which can lead to radiative heat loss and reduced confinement. This study explores the clustering of heavy impurity, i.e. tungsten in edge plasma, using hi…

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Breeder blanket and tritium fuel cycle feasibility of the Infinity Two fusion pilot plant

Journal of Plasma Physics

The selection, design and optimization of a suitable blanket configuration for an advanced high-field stellarator concept is seen as a key feasibility issue and has been incorporated as a vital and necessary part of the Infinity Two fusion pilot plant physi…

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Advancements in Nuclear Fusion: Towards Sustainable Energy Production

Journal of the West

Many people believe that the only way to meet the world's increasing energy needs is through nuclear fusion, which is the release of energy through the combination of atomic nuclei. Nuclear fusion has the ability to provide almost endless amounts of clean e…

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In-situ calibration of neutron flux monitor for HL-3 tokamak

Nuclear Fusion

Abstract This paper reports the rapid in-situ calibration of neutron flux monitors completed on the HL-3 tokamak device, a process that took only 14 h. The efficiency of the detection system, consisting of B-10 proportional counters and U-235 fission chambe…

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Plasma-Facing Materials for Fusion Energy: Historical Review, Challenges and Future Directions

Extreme Materials

The promise of fusion energy is real. Major countries worldwide aim to achieve commercial grid-connected fusion power generation by around 2050, with magnetic confinement fusion—represented by tokamaks—leading the way among various fusion approaches. Howeve…

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Study and analysis of ion cyclotron resonance heating scenarios for ADITYA-U Tokamak

Nuclear Fusion

Abstract This study provides a detailed analysis of ion cyclotron resonance heating (ICRH) scenarios for ADITYA-U Tokamak which is a crucial technique for core plasma heating in magnetically confined devices. The ICRH code LION is used to study the cyclotro…

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Gyrokinetic simulations of magnetohydrodynamic modes in stellarator plasmas

Journal of Plasma Physics

Abstract 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…

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Opportunities in pulsed magnetic fusion energy

Physics of Plasmas

Fusion is a potentially transformational energy technology, which promises limitless clean energy. Yet, it requires continued scientific and technological development to realize its potential. The conditions necessary for fusion energy gain in terms of the…

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Preventing a Tokamak from Overheating

Physics

Preventing a Tokamak from OverheatingFusion reactor experiments in Switzerland have demonstrated a new way to remove unwanted heat from a magnetically confined plasma. By Charles DayA mong the most enduring designs for a fusion reactor is the tokamak, which…

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Demonstration of Super-X divertor exhaust control for transient heat load management in compact fusion reactors

Nature Energy

Abstract Nuclear fusion could offer clean, abundant energy. However, managing the power exhausted from the core fusion plasma towards the reactor wall remains a major challenge. This is compounded in emerging compact reactor designs promising more cost-effe…

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Implementation of an ITER-relevant QP-based current limit avoidance algorithm in the TCV tokamak

Plasma Physics and Controlled Fusion

Abstract The problem of avoiding saturation of the coil currents is critical in large tokamaks with superconducting coils like ITER. Indeed, if the current limits are reached, a loss of control of the plasma may lead to a major disruption. Therefore, a curr…

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Variety of coil sets for the compact stellarator-tokamak hybrid

Plasma Physics and Controlled Fusion

Abstract A first of-its-kind quasi-axisymmetric stellarator-tokamak hybrid design concept has recently been presented (Henneberg and Plunk 2024 Phys. Rev. Res. 6 L022052). Here we will provide an overview of various coil configurations that can be employed…

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Preliminary measurements of alpha particles produced by proton-boron nuclear fusion reaction on Z-pinch type discharges

Plasma Physics and Controlled Fusion

Abstract The 11 B(p, α )2 α fusion reaction occurring in hydrogen-boron fuel seems to be the most promising, therefore it is currently being investigated in various systems such as magnetic confinement fusion, inertial confinement fusion, high-power lasers…

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Turbulent Transport-Limited Pedestals in Tokamaks

arXiv (Cornell University)

H-mode operation of tokamak fusion plasmas free of dangerous Type 1 edge-localized-modes (ELMs) requires a non-ELM mechanism for saturating the edge pedestal growth. One possible mechanism is turbulent transport. We introduce a transport threshold model to…

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Impurity effects on the coupling of TEM and ITG mode in tokamak deuterium–tritium mixture plasmas

Physics of Plasmas

The gyrokinetic integral eigenvalue equation is extended to include the mixing of hydrogen isotopes, deuterium and tritium ions, as the main ion species. Impurity effects on the coupling of the trapped electron mode (TEM) and ion temperature gradient (ITG)…

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Combining physics-based and data-driven models for quantitatively accurate plasma profile prediction that extrapolates well; with application to DIII-D, AUG, and ITER tokamaks

Nuclear Fusion

Abstract For design, scenario planning, and control, ITER and all other envisioned tokamaks rely on a variety of statistical and physics-based models to extrapolate to unseen regimes; most notably from low plasma current to high. A ‘meta-learning’ methodolo…

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Surface loss probabilities of boron-hydride radicals in W7-X and ASDEX Upgrade

Nuclear Materials and Energy

• The surface loss probabilities of boron hydride radicals created in boronisation plasmas in W7-X and ASDEX Upgrade were determined experimentally using the cavity technique. • The incident flux responsible for the growth of boron layers consists predomina…

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Simulation of fusion neutron spectra from D-D and D-T thermonuclear fusion

Scientific Reports

Investigating the neutron spectra produced by thermonuclear fusion reactions D(d , n) 3 He and T(d , n) 4 He , which will power the future fusion reactors, is a critical factor in improving the performance of fusion reactors. Experimentally, it is extremely…

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Offline Reinforcement Learning for Rotation Profile Control in Tokamaks

arXiv (Cornell University)

Tokamaks remain leading candidates for achieving practical fusion energy, yet many important control problems inside these devices are still difficult or unsolved. One such challenge is controlling the plasma rotation profile, which strongly influences stab…

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