Default: Journal of Nuclear Materials

ISSN: 0022-3115

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Journal of Nuclear Materials Q1 Unclaimed

Elsevier Netherlands
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Journal of Nuclear Materials is a journal indexed in SJR in Materials Science (miscellaneous) and Nuclear Energy and Engineering with an H index of 132. It has an SJR impact factor of 0,98 and it has a best quartile of Q1. It is published in English.

Type: Journal

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Languages: English

Open Access Policy:

Type of publications:

Publication frecuency: -


Journal of Nuclear Materials


SJR Impact factor


H Index


Total Docs (Last Year)


Total Docs (3 years)


Total Refs


Total Cites (3 years)


Citable Docs (3 years)


Cites/Doc (2 years)



Best articles

A fast scanning Langmuir probe system for ASDEX-Upgrade divertor

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A method to study deformation mechanisms for irradiated steels using a disk-bend test

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A Mossbauer study of single-crystal Zr-0.065 at% 57Fe

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A novel technique to remove deuterium from CANDU pressure tubes

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A swelling model for stoichiometric SiC at temperatures below 1000ºC under neutron irradiation

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Ab initio MO study on hydrogen release from surface of lithium silicate

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Activation of stainless steel with high energy neutrons

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An unified model of steady-state segregation in multicomponent alloys

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Analysis and characterization of plutonium in pyrochemical salt residues

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Be-Cu joints based on amorphous alloy brazing for divertor and first wall application

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Beta radiation effects in 137Cs-substituted pollucite

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Blister formation by 30 MeV helium ion irradiation in Ni-1% Cu

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Characterization of U-Nb-Zr dispersion fuel prepared by centrifugal atomization process

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Chemical reactions of dicaesium telluride, Cs2Te, and of dicaesium telluride/caesium mixtures with zirconium and with Zircaloy-4

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Collision cascades in metals and semiconductors: defect creation and interface behavior

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Conductivity of fission-damaged uranium nitride

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Current status of SiC/SiC composites R&D

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Defect structure development in a pure iron and dilute iron alloys irradiated with neutrons and electrons

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Dependence of the non-swelling in-reactor steady-state creep component of austenitic phase alloys on the stacking fault energy

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Depth distribution of deuterium atoms and molecules in beryllium oxide implanted with deuterium ions

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Design study of an irradiation experiment with inert matrix and mixed-oxide fuel at the Halden boiling water reactor

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Destination of point defects and microstructural evolution under collision cascade damage

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Deuterium distributions on delayed hydride crack fracture surfaces of Zr-2.5Nb

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Deuterium in re-deposited silicon-doped carbon layers and its removal by heating in air

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