ISSN: 0920-3796
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Fusion Engineering and Design Q2 Unclaimed
Fusion Engineering and Design is a journal indexed in SJR in Materials Science (miscellaneous) and Mechanical Engineering with an H index of 87. It has an SJR impact factor of 0,672 and it has a best quartile of Q2. It is published in English. It has an SJR impact factor of 0,672.
Type: Journal
Type of Copyright:
Languages: English
Open Access Policy:
Type of publications:
Publication frecuency: -
- €
Inmediate OANPD
Embargoed OA- €
Non OAMetrics
0,672
SJR Impact factor87
H Index265
Total Docs (Last Year)2300
Total Docs (3 years)7289
Total Refs3706
Total Cites (3 years)2299
Citable Docs (3 years)1.66
Cites/Doc (2 years)27.51
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Aims and Scope
Best articles by citations
Thermal fatigue tests on disruption-damaged first-wall components
View moreExperimental and calculational studies of non-uniform shieldings of fusion reactors
View moreMeasurement of density fluctuations by JFT-2M reflectometer
View moreTemperature fluctuation measurements with ECE at W7-AS
View moreBoundary layer physics considerations for the TEXTOR dynamic ergodic divertor experiment
View moreLow energy (0.5-3 keV) fast neutral lithium beam source for edge plasma density measurements
View moreDesign of a steady-state tokamak device with superconducting coils for a volumetric neutron source
View moreNext generation discharge control system for ASDEX upgrade
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 moreECR - discharge cleaning for TRIAM - 1M
View moreDesign, construction and the first plasma experiments in the Large Helical Device
View moreBeryllium application in ITER plasma facing components
View moreITER reference breeding blanket design
View moreDensity fluctuations in Heliotron E measured using C02 laser phase contrast method
View moreDesign of ITER neutron yield monitor using microfission chambers
View moreITER: the first experimental fusion reactor
View moreEnvironmental aspects of tritium and active waste - A comparison of four inertial confinement fusion reactor concepts
View moreDevelopment of 15-m-long radiation hard periscope for ITER in-vessel viewing
View moreReduction of toroidal ripple by using high Tc superconductors
View moreSome engineering aspects of high heat flux components for volumetric neutron source based on spherical torus
View moreRussian DEMO plant study
View moreA novel method of TVTS in the TS-3 device and the proposal of its application to a large device
View moreObservation of implosion dynamics by line emissions from direct-drive fusion capsules
View moreX-ray diagnostics for investigating electron distribution functions and electron potential confinements
View more
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