Nuclear Fusion

Nuclear Fusion is the acknowledged world-leading journal specializing in fusion. The journal covers all aspects of research, theoretical and practical, relevant to controlled thermonuclear fusion.

公式サイト

Impact Factor

Citescore

3.2

最新論文

Current ramp-up studies for NSTX-U in support of the development of non-inductive current ramp-up scenarios in STs
The impact of kinetic and global effects on ideal ballooning 2nd stable pedestals of conventional and low aspect-ratio tokamaks
Boundary turbulence simulations of the optimized HSX stellarator and comparison with experiments
Enabling integrated AI control on DIII-D: a control system design with state-of-the-art experiments
Ex situ investigation of boron, hydrogen, and oxygen distributions on W7-X divertor surfaces using picosecond-LIBS under vacuum

AI解説分析論文一覧

Nuclear Fusion

最新論文

Nuclear Fusion

最新論文

Effect of the limiter position on the scrape-off layer width, radial electric field and intrinsic flows

Effect of layer thickness on the thermal release from Be–D co-deposited layers

Visible light tomography of MHD eigenmodes in the H-1NF stellarator using magnetic coordinates

Fast generation of an inward electric field due to ion orbit losses in the tokamak edge plasma during transition from low-to-high confinement

Preliminary corrosion studies of P-91 in flowing lead–lithium with and without magnetic field for Indian lead–lithium ceramic breeder test blanket module

Tungsten transport in JET H-mode plasmas in hybrid scenario, experimental observations and modelling

Inter-machine comparison of the termination phase and energy conversion in tokamak disruptions with runaway current plateau formation and implications for ITER

Suppression of cavitation in melted tungsten by doping with lanthanum oxide

Non-local heat transport in Alcator C-Mod ohmic L-mode plasmas

Application of very high harmonic fast waves for off-axis current drive in the DIII-D and FNSF-AT tokamaks

A novel approach for mitigating disruptions using biased electrode in Aditya tokamak

Characterization of scrape-off layer transport in JET limiter plasmas

Progress in understanding the enhanced pedestal H-mode in NSTX

Comparison of measured impurity poloidal rotation in DIII-D with neoclassical predictions under low toroidal field conditions

Reduction of core turbulence in I-mode plasmas in Alcator C-Mod

On the interaction between the ion cyclotron resonance heating and scrape-off layer turbulence via coherent waves

Inboard and outboard radial electric field wells in the H- and I-mode pedestal of Alcator C-Mod and poloidal variations of impurity temperature

Low initial aspect-ratio direct-drive target designs for shock- or self-ignition in the context of the laser Megajoule

On the conditions for up–down asymmetry in the core of tokamak equilibria: a matter of simple geometry

Surface morphology and deuterium retention of tungsten after low- and high-flux deuterium plasma exposure

Ultrafine tungsten as a plasma-facing component in fusion devices: effect of high flux, high fluence low energy helium irradiation

Characteristics of global energy confinement in KSTAR L- and H-mode plasmas

Impurity density derivation from bandpass soft x-ray tomography: applicability, perspectives and limitations

Improved accuracy in the estimation of the tearing mode stability parameters (Δ' and wc) using 2D ECEI data in KSTAR

ELM pacing and high-density operation using pellet injection in the ASDEX Upgrade all-metal-wall tokamak

Effects of centrifugal modification of magnetohydrodynamic equilibrium on resistive wall mode stability

Three-dimensional distortions of the tokamak plasma boundary: boundary displacements in the presence of saturated MHD instabilities

Three-dimensional distortions of the tokamak plasma boundary: boundary displacements in the presence of resonant magnetic perturbations

Non-linear wave-particle interactions and fast ion loss induced by multiple Alfvén eigenmodes in the DIII-D tokamak

Full wave simulations of fast wave heating losses in the scrape-off layer of NSTX and NSTX-U