Fusion Engineering and Design

Papers
(The H4-Index of Fusion Engineering and Design is 27. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2021-10-01 to 2025-10-01.)
ArticleCitations
Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR)105
Soft X-ray tomography using the optimized regularization method in Alvand Tokamak82
Upgrade of the cathode HVPS system for 4.6 GHz LHCD on EAST using high speed PSM76
The wide-angle infrared diagnostic for the first wall monitoring of the WEST tokamak64
Numerical calculations on liquid-metal magnetohydrodynamic flow in rectangular channel with wavelike uneven walls60
Editorial Board56
Editorial Board55
Mode purity evaluation of high-power millimeter wave transmission line by 3-port directional coupler52
Influence of temperature gradients on helium diffusion and clustering in tungsten: A molecular dynamics study47
Investigation of heat treatment to remove carbon on alumino-silicate fiber and mechanical and insulation properties of alumino-silicate fiber composites used at Bi-2212 CICC45
Design and engineering challenges of a multi-energy hard x-ray camera for long-pulse profile measurements at WEST tokamak43
Editorial Board42
Updating the build, test, and deploy systems for MDSplus41
Kinetic study on leaching process of beryl with basic solution under microwave heating40
Front face shaping of the inner wall tiles in the COMPASS Upgrade tokamak38
Proposal of new electrode supports in NBI for breakdown incidence reduction38
Supporting analysis for WCLL test blanket system safety38
Microstructure and properties of La2O3-doped tungsten-based bulk material and its densification mechanism during spark plasma sintering process37
Methodology for radiofrequency electromagnetic analysis in the engineering of ITER Electron Cyclotron Heating Upper Launcher36
Shutdown dose rate assessment of the interspace components of wide angle viewing system diagnostic for ITER35
Performance of fine-grained W/Cu plate prepared by explosive welding with high wave impedance confinement at room temperature33
Study of non-convergence problem of the integral method for polarizer design on the ECRH system32
Design of ITER neutron flux monitor system back-end electronics31
Improved strength and heat transfer of W/Cu joints via surface nano-activation of W30
ITER DMS fast shutter prototype testing30
Design of the removable shrouds for inertial-confinement-fusion cryotargets30
Electromagnetic preliminary design of the real-time millimetre-wave radar system for the diagnostic of the IFMIF-DONES lithium target29
The Tritium Extraction eXperiment (TEX): A forced convection fusion blanket PbLi loop27
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