ISSN: 0920-3796

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Fusion Engineering and Design Q2 Unclaimed

Elsevier B.V. Netherlands

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Fusion Engineering and Design is a journal indexed in SJR in Materials Science (miscellaneous) and Mechanical Engineering with an H index of 91. It has an SJR impact factor of 0,563 and it has a best quartile of Q2. It is published in English. It has an SJR impact factor of 0,563.

Type: Journal

Type of Copyright:

Languages: English

Open Access Policy:

Type of publications:

Publication frecuency: -

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

Price

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Inmediate OA

NPD

Embargoed OA

- €

Non OA

Metrics

0,563

SJR Impact factor

91

H Index

627

Total Docs (Last Year)

1655

Total Docs (3 years)

13910

Total Refs

3119

Total Cites (3 years)

1648

Citable Docs (3 years)

1.99

Cites/Doc (2 years)

22.19

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

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Aims and Scope

Best articles by citations

Thermal fatigue tests on disruption-damaged first-wall components

Experimental and calculational studies of non-uniform shieldings of fusion reactors

Measurement of density fluctuations by JFT-2M reflectometer

Temperature fluctuation measurements with ECE at W7-AS

Boundary layer physics considerations for the TEXTOR dynamic ergodic divertor experiment

Low energy (0.5-3 keV) fast neutral lithium beam source for edge plasma density measurements

Design of a steady-state tokamak device with superconducting coils for a volumetric neutron source

Next generation discharge control system for ASDEX upgrade

Characteristic 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

ECR - discharge cleaning for TRIAM - 1M

Design, construction and the first plasma experiments in the Large Helical Device

Beryllium application in ITER plasma facing components

SHOW MORE ARTICLES

ITER reference breeding blanket design

Density fluctuations in Heliotron E measured using C02 laser phase contrast method

Design of ITER neutron yield monitor using microfission chambers

ITER: the first experimental fusion reactor

Environmental aspects of tritium and active waste - A comparison of four inertial confinement fusion reactor concepts

Development of 15-m-long radiation hard periscope for ITER in-vessel viewing

Reduction of toroidal ripple by using high Tc superconductors

Some engineering aspects of high heat flux components for volumetric neutron source based on spherical torus

Russian DEMO plant study

A novel method of TVTS in the TS-3 device and the proposal of its application to a large device

Observation of implosion dynamics by line emissions from direct-drive fusion capsules

X-ray diagnostics for investigating electron distribution functions and electron potential confinements