Fusion Engineering and Design
Fusion Engineering and Design is a journal indexed in SJR in Materials Science (miscellaneous) and Mechanical Engineering with an H index of 95. It has an SJR impact factor of 0,727 and it has a best quartile of Q1. It is published in English. It has an SJR impact factor of 0,727.
Metrics
Scimago and CountryOfPapers database fields
SJR Impact
0,727
H-index
95
Docs (year)
535
Docs 3y
1654
Total refs
13034
Cites 3y
3390
Citable 3y
1645
Cites/Doc 2y
2.04
Ref/Doc
24.36
Immediate OA
—
Embargoed OA
NPD
Non OA / Submission
—
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Researcher reviews
Best articles by citations
Boundary layer physics considerations for the TEXTOR dynamic ergodic divertor experiment
View moreX-ray diagnostics for investigating electron distribution functions and electron potential confinements
View moreDevelopment of a nuclear-thermal coupled calculation code system
View moreDevelopment of 15-m-long radiation hard periscope for ITER in-vessel viewing
View moreDesign, construction and the first plasma experiments in the Large Helical Device
View moreDesign study of a tritium transport package for future fusion reactors
View moreDesign of separated first wall for fusion experimental reactor
View moreDesign of ITER neutron yield monitor using microfission chambers
View moreDesign of a steady-state tokamak device with superconducting coils for a volumetric neutron source
View moreDensity fluctuations in Heliotron E measured using C02 laser phase contrast method
View moreData analysis software tools for enhanced collaboration at the DIII-D National Fusion Facility
View moreData analysis software on the FTU experiment and its recent developments
View moreCharacteristic parameters of the magnetic field due to the dynamic ergodic divertor1Correspondence: K.H. Finken, Institut for Plasma Physics, Forschungszentrum Juelich, Association EURATOM-KFA, D-52415 Juelich, Germany1
View more2 MV injector as the Elise front-end and as an experimental facility
View moreBeryllium application in ITER plasma facing components
View moreBenchmarking of evaluated nuclear data for bismuth by spherical shell transmission experiments with central T(d,n) and Cf-252 neutron sources
View moreApplications of the CATHARE and CONTAIN codes in parallel runs
View moreAnalysis of tritium transport in irradiated beryllium
View moreAnalysis of the tokamak volumetric neutron source (VNS) design and range of its parameters
View moreAnalysis and experimental results on ingress of coolant event in vacuum vessel
View moreAdvanced electron cyclotron heating systems for next-step fusion experiments
View moreA volumetric neutron source for fusion nuclear technology testing and development
View moreA power supply system for a 125 keV/250 keV neutral beam injector test stand based on negative ion sources
View moreA novel method of TVTS in the TS-3 device and the proposal of its application to a large device
View more