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verified SJR 0,453 · Q2 • database Scopus / SJR & Web of Science indexed
Fusion Science and Technology
United States · Taylor and Francis Ltd.
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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.

ISSN: 1536-1055
Publisher: Taylor and Francis Ltd.
Category: Materials Science (miscellaneous)
Indexation: verifiedScopus / SJR verifiedWeb of Science
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schedule CountryOfPapers database fields
SJR Impact Factor trending_up
0,453 Q2
H-index 61
Acceptance rate pie_chart
30% Selective
Source Acceptance_Rate
Time to publication hourglass_top
NPD
Field NPD
Publication cost (APC) payments
NPD Subscription
Non-OA path NPD

Metrics

Scimago and CountryOfPapers database fields

Scopus / SJR Web of Science

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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Best articles by citations

Safety Assessment of the ARIES Compact Stellarator Design

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Hydrogen Isotope Separation Using Molecular Sieve of Synthetic Zeolite 3A

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Integration of the Modular Dual Coolant Pb-17Li Blanket Concept in the ARIES-CS Power Plant

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Mechanical Properties of beta-SiC After Si- and Dual Si + He-Ion Irradiation at Various Temperatures

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National Ignition Facility Laser System Performance

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Neutronics Characteristics and Shielding System for ARIES-ACT1 Power Plant

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On the Mechanism of the Disproportionation of ZrCo Hydrides

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Performance of Plasma-Facing Materials Under Intense Thermal Loads in Tokamaks and Stellarators

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Physics Basis for a Conservative Physics and Conservative Technology Tokamak Power Plant: ARIES-ACT2

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Physics Basis for an Advanced Physics and Advanced Technology Tokamak Power Plant Configuration: ARIES-ACT1

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Plasma Heat-Flux Dispersal for ACT1 Divertor Configurations

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Progress in Experimental Research of the Vasimr Engine

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Progress in SiC-Based Ceramic Composites for Fusion Applications

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Helium Accumulation Behavior in Iron Based Model Alloys

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State-of-the-Art 3-D Assessment of Elements Degrading the TBR of the ARIES DCLL Blanket

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Study on Tritium Balance in a D-T Fusion Reactor

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The Effect of 3He on Low Pressure Hydride Absorption Measurements with Tritium

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The Evaluation of the Heat Loading from Steady, Transient and Off-Normal Conditions in ARIES Power Plants

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Thermal Discrete Element Analysis of EU Solid Breeder Blanket Subjected to Neutron Irradiation

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Thermomechanical Analysis for an All-Tungsten ARIES Divertor

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Tritium Challenges and Plans for ITER Pellet Fueling and Disruption Mitigation Systems

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Tritium Retention in Hexavalent Chromate-Conversion-Coated Aluminum Alloy

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Vacuum Vessel Analysis and Design for the ARIES-ACT1 Fusion Power Plant

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Verification of Thermal Performance Predictions of Prototypical Multi-Jet Impingement Helium-Cooled Divertor Module

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