Fusion Science and Technology
Fusion Science and Technology is a journal indexed in SJR in Materials Science (miscellaneous) and Mechanical Engineering with an H index of 61. It has an SJR impact factor of 0,453 and it has a best quartile of Q2. It is published in English. It has an SJR impact factor of 0,453.
Metrics
Scimago and CountryOfPapers database fields
SJR Impact
0,453
H-index
61
Docs (year)
126
Docs 3y
274
Total refs
3445
Cites 3y
357
Citable 3y
267
Cites/Doc 2y
1.34
Ref/Doc
27.34
Immediate OA
—
Embargoed OA
NPD
Non OA / Submission
—
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Researcher reviews
Best articles by citations
Safety Assessment of the ARIES Compact Stellarator Design
View moreHydrogen Isotope Separation Using Molecular Sieve of Synthetic Zeolite 3A
View moreIntegration of the Modular Dual Coolant Pb-17Li Blanket Concept in the ARIES-CS Power Plant
View moreMechanical Properties of beta-SiC After Si- and Dual Si + He-Ion Irradiation at Various Temperatures
View moreNational Ignition Facility Laser System Performance
View moreNeutronics Characteristics and Shielding System for ARIES-ACT1 Power Plant
View moreOn the Mechanism of the Disproportionation of ZrCo Hydrides
View morePerformance of Plasma-Facing Materials Under Intense Thermal Loads in Tokamaks and Stellarators
View morePhysics Basis for a Conservative Physics and Conservative Technology Tokamak Power Plant: ARIES-ACT2
View morePhysics Basis for an Advanced Physics and Advanced Technology Tokamak Power Plant Configuration: ARIES-ACT1
View morePlasma Heat-Flux Dispersal for ACT1 Divertor Configurations
View moreProgress in Experimental Research of the Vasimr Engine
View moreProgress in SiC-Based Ceramic Composites for Fusion Applications
View moreHelium Accumulation Behavior in Iron Based Model Alloys
View moreState-of-the-Art 3-D Assessment of Elements Degrading the TBR of the ARIES DCLL Blanket
View moreStudy on Tritium Balance in a D-T Fusion Reactor
View moreThe Effect of 3He on Low Pressure Hydride Absorption Measurements with Tritium
View moreThe Evaluation of the Heat Loading from Steady, Transient and Off-Normal Conditions in ARIES Power Plants
View moreThermal Discrete Element Analysis of EU Solid Breeder Blanket Subjected to Neutron Irradiation
View moreThermomechanical Analysis for an All-Tungsten ARIES Divertor
View moreTritium Challenges and Plans for ITER Pellet Fueling and Disruption Mitigation Systems
View moreTritium Retention in Hexavalent Chromate-Conversion-Coated Aluminum Alloy
View moreVacuum Vessel Analysis and Design for the ARIES-ACT1 Fusion Power Plant
View moreVerification of Thermal Performance Predictions of Prototypical Multi-Jet Impingement Helium-Cooled Divertor Module
View more