ISSN: 1536-1055

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Fusion Science and Technology Q2 Unclaimed

Taylor and Francis Ltd. United States

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Fusion Science and Technology is a journal indexed in SJR in Materials Science (miscellaneous) and Mechanical Engineering with an H index of 58. It has an SJR impact factor of 0,355 and it has a best quartile of Q2. It is published in English. It has an SJR impact factor of 0,355.

Type: Journal

Type of Copyright:

Languages: English

Open Access Policy:

Type of publications:

Publication frecuency: -

Categories: Nuclear Energy and Engineering (Q2) Civil and Structural Engineering (Q3) Materials Science (miscellaneous) (Q3) Mechanical Engineering (Q3) Nuclear and High Energy Physics (Q3)

Price

- €

Inmediate OA

NPD

Embargoed OA

- €

Non OA

Metrics

0,355

SJR Impact factor

58

H Index

185

Total Docs (Last Year)

277

Total Docs (3 years)

4921

Total Refs

300

Total Cites (3 years)

274

Citable Docs (3 years)

0.97

Cites/Doc (2 years)

26.6

Ref/Doc

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Materialia Q2
Aerosol Science and Technology Q2
Journal of Physics and Chemistry of Solids Q2
JVC/Journal of Vibration and Control Q2
Journal of Physics Condensed Matter Q2

Compare this journals

Aims and Scope

Best articles by citations

Experimental Studies of the Thermal Performance of Gas-Cooled Plate-Type Divertors

Thermomechanical Analysis for an All-Tungsten ARIES Divertor

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

Experimental Evaluation of the Thermal Hydraulics of Helium-Cooled Divertors

Progress in Experimental Research of the Vasimr Engine

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

Tritium Retention in Hexavalent Chromate-Conversion-Coated Aluminum Alloy

Evolution of Clearance Standards and Implications for Radwaste Management of Fusion Power Plants

Study on Tritium Balance in a D-T Fusion Reactor

Chapter 12: Generic Diagnostic Issues for a Burning Plasma Experiment

Activation and Environmental Aspects of ARIES-ACT1 Power Plant

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

SHOW MORE ARTICLES

Hydrogen Isotope Separation Using Molecular Sieve of Synthetic Zeolite 3A

Helium Accumulation Behavior in Iron Based Model Alloys

Development of ITER Divertor Vertical Target with Annular Flow Concept - I: Thermal-Hydraulic Characteristics of Annular Swirl Tube

An Analytic Expression for the Tritium Burnup Fraction in Burning-Plasma Devices

Development Status of a SiC-Foam Based Flow Channel Insert for a U.S.-ITER DCLL TBM

Dynamics of Small Mobile Helium Clusters Near a Symmetric Tilt Grain Boundary of Plasma-Exposed Tungsten

Progress in SiC-Based Ceramic Composites for Fusion Applications

ARIES-ACT1 Power Core Engineering

ARIES-ACT1 Safety Design and Analysis

ARIES-ACT1 System Configuration, Assembly, and Maintenance

ARIES-ACT2 DCLL Power Core Design and Engineering

Development of the Lead Lithium (DCLL) Blanket Concept