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

Three-dimensional Monte Carlo simulations of W7-X plasma transport: density control and particle balance in steady-state operations

Advanced ST plasma scenario simulations for NSTX

Effect of the resistive wall on the growth rate of weakly unstable external kink mode in general 3D configurations

Plasma confinement using biased electrode in the TCABR tokamak

R&D on a high energy accelerator and a large negative ion source for ITER

Status of the KSTAR superconducting magnet system development

RF current distribution and topology of RF sheath potentials in front of ICRF antennae

Reynolds and Maxwell stress measurements in the reversed field pinch experiment Extrap-T2R

Helium ash removal from stellarator-reactor by lower hybrid waves

Advances in comprehensive gyrokinetic simulations of transport in tokamaks

PIES free boundary stellarator equilibria with improved initial conditions

Studies of the 'Quiescent H-mode' regime in ASDEX Upgrade and JET

On the parasitic absorption in FWCD experiments in JET ITB plasmas

Electron cyclotron heating assisted startup in JT-60U

Effects of wall boron coating on FTU, an all metallic and carbon free medium size tokamak

Eddy currents in the vacuum vessel of the ETE spherical tokamak

Suppression of blister formation and deuterium retention on tungsten surface due to mechanical polishing and helium pre-exposure

Neutronic analysis for the EU water-cooled lithium–lead test blanket module in ITER-FEAT

Experimental studies on tungsten-armour impact on nuclear responses of solid breeding blanket

Towards reduced activation structural materials data for fusion DEMO reactors

Importance of electron cyclotron wave energy transport in ITER

Assessment of plastic flow and fracture properties with small specimen test techniques for IFMIF-designed specimens

The 'hybrid' scenario in JET: towards its validation for ITER

The improved H-mode at ASDEX Upgrade: a candidate for an ITER hybrid scenario

Effect of neutral transport on ITER divertor performance

Suppression of large edge localized modes with edge resonant magnetic fields in high confinement DIII-D plasmas

Formation and healing of n = 1 magnetic islands in LHD equilibrium

Modelling of ITER improved H-mode operation with the integrated core pedestal SOL model

Stationary high confinement plasmas with large bootstrap current fraction in JT-60U

High-ion temperature experiments with negative-ion-based neutral beam injection heating in Large Helical Device