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Tungsten erosion during L-mode discharges in the DIII-D SAS-VW divertor
Published 2025-03-01Subjects: Get full text
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22
Investigation of divertor heat flux characteristics under the influence of resonant magnetic perturbations on EAST
Published 2025-01-01Subjects: “…tokamak…”
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23
The design and implementation of automated maintenance system for the first-wall based on dual-arm manipulator
Published 2025-02-01Subjects: “…Tokamak device…”
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24
Transport and profile broadening in the private flux region of ASDEX upgrade and role for power exhaust
Published 2025-01-01“…Understanding the transport processes that determine the plasma profile widths in the scrape-off layer (SOL) and divertor region of tokamaks is crucial for successful power and particle exhaust management in future devices. …”
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25
Comparison of plasma start-up with high Z and low Z first wall in WEST
Published 2025-01-01“…In this context, the present work focuses on the correlations between first wall impurity sources and total radiated power during plasma start-up in the tungsten (W) Environment in Steady-state Tokamak (WEST). The objective is to highlight experimental indications for a preferable combination of start-up plasma scenario and first wall materials. …”
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26
The quasi-continuous exhaust regime in JET
Published 2025-01-01“…Porting the QCE regime to JET strongly benefited from the experimental and modelling efforts at the medium sized tokamaks ASDEX Upgrade and TCV. Using the physics picture developed from the ASDEX Upgrade experimental results, the route to the QCE regime in JET reported here is following closely the approach that was successful in ASDEX Upgrade. …”
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27
Doubling fusion power with volumetric optimization in magnetic confinement fusion devices
Published 2025-02-01“…A technique, volumetric power optimization, is presented for enhancing the power output of magnetic confinement fusion devices. Applied to a tokamak, this approach involves shifting the burning plasma region to a larger plasma volume while introducing minimal perturbations to the plasma boundary shape. …”
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28
Cross-code comparison of the edge codes SOLPS-ITER, SOLEDGE2D and UEDGE in modelling a high-power neon-seeded scenario in the DTT
Published 2025-01-01“…In this work, we cross-compare the state-of-the-art edge plasma codes SOLPS-ITER, SOLEDGE2D, and UEDGE in a reactor-relevant neon-seeded Divertor Tokamak Test scenario at nominal power, extending the simplified test-bed of Moscheni et al (2022 Nucl. …”
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Development of a Remote Handling Robot for the Maintenance of an ITER-Like D-Shaped Vessel
Published 2014-01-01“…Robotic operation is one of the major challenges in the remote maintenance of ITER vacuum vessel (VV) and future fusion reactors as inner operations of Tokamak have to be done by robots due to the internal adverse conditions. …”
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Nonlinear excitation of energetic particle driven geodesic acoustic mode by resonance overlap with Alfvén instability in ASDEX Upgrade
Published 2025-01-01“…Abstract The Alfvén instability nonlinearly excited the energetic-particle-driven geodesic acoustic mode on the ASDEX-Upgrade tokamak, as demonstrated experimentally. The mechanism of the energetic-particle-driven geodesic acoustic mode excitation and the mode nonlinear evolution is not yet fully understood. …”
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31
Estimation of neutral beam injector power transferred to KSTAR plasmas
Published 2025-02-01“…In a long pulse operation, the water coolant temperature is at the steady state condition in longer pulse more than 20s and the coupled neutral beam power to KSTAR plasma during the tokamak experiments is rechecked by using water flow calorimetric method after the experiment. …”
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32
Coil optimization methods for a planar coil stellarator
Published 2025-01-01“…The plasma encircling coils provide the mean magnetic field and linking current, similar to the toroidal field (TF) coils in a tokamak. The plasma encircling coils can be rotationally symmetric TF-like coils and produce a $B\propto 1/R$ field, but optimizing their placement, tilt, and shaping can substantially reduce the magnetic field error. …”
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Development of Vacuum Vessel Design and Analysis Module for CFETR Integration Design Platform
Published 2016-01-01“…The integration engineering design platform aims at performing detailed engineering design for each tokamak component (e.g., breeding blanket, divertor, and vacuum vessel). …”
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35
Effect of plasma beta on the nonlinear evolution of m/n = 2/1 double tearing mode in high Lundquist number regime
Published 2025-01-01“…Furthermore, a preliminary case study shows that the tokamak plasma rotation shear has a significant impact on plasmoid dynamic.…”
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36
A new continuous optimization method of standardized cubic permanent magnets for stellarators
Published 2025-01-01“…Stellarator configurations can be realized using permanent magnets in combination with tokamak-like planar coils. From the perspective of engineering feasibility and cost-effectiveness, using standardized cubic permanent magnets with a finite number of magnetization directions is particularly advantageous. …”
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37
Gyrokinetic simulations of the effects of magnetic islands on microturbulence in KSTAR
Published 2025-01-01“…Gyrokinetic simulations are utilized to study effects of magnetic islands (MIs) on the ion temperature gradient (ITG) turbulence in the KSTAR tokamak with resonant magnetic perturbations. Simulations show that the transport is controlled by the nonlinear interactions between the ITG turbulence and self-generated vortex flows and zonal flows, leading to an anisotropic structure of fluctuation and transport on the poloidal plane and in the toroidal direction. …”
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38
Fast electrons produced by lower hybrid wave and effects on plasma–wall interactions
Published 2025-01-01“…Lower hybrid wave (LHW) current drive plays a crucial role in sustaining steady-state (SS) discharges on the Experimental Advanced Superconducting Tokamak (EAST). Hotspots frequently form on the wave antenna and guard limiters during SS operations. …”
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39
Infernal instabilities in negative-triangularity plasmas with negative central shear
Published 2025-01-01“…A systematic numerical investigation is carried out to understand magnetohydrodynamic stability of the ideal infernal-kink instability in tokamak plasmas with both negative triangularity (neg-D) shaping and negative central shear for the equilibrium safety factor profile. …”
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40
Amorphization and siliconization of silicon carbide as a first wall material
Published 2025-01-01“…Gross and net Si erosion rates from SiC surfaces in contact with a well-diagnosed L-mode plasma in the DIII-D tokamak have been simulated and the surface concentrations of impurities have been tracked as a function of time. …”
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