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

Type of Copyright:

Languages: English

Open Access Policy:

Type of publications:

Publication frecuency: -

Categories: Materials Science (miscellaneous) (Q1) Nuclear and High Energy Physics (Q1) Nuclear Energy and Engineering (Q1)

Price

- €

Gold OA

-

Green OA

- €

Non OA

Metrics

0,98

SJR Impact factor

132

H Index

571

Total Docs (Last Year)

1868

Total Docs (3 years)

27491

Total Refs

5228

Total Cites (3 years)

1839

Citable Docs (3 years)

2,72

Cites/Doc (2 years)

48,15

Ref/Doc

Aims and Scope

Other journals with similar parameters

Advanced Energy Materials Q1
Nano Futures Q1
Nano Futures Q1
Annual Review of Condensed Matter Physics Q1
Progress in Materials Science Q1

Best articles

A fast scanning Langmuir probe system for ASDEX-Upgrade divertor

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

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

A novel technique to remove deuterium from CANDU pressure tubes

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

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

Activation of stainless steel with high energy neutrons

An unified model of steady-state segregation in multicomponent alloys

Analysis and characterization of plutonium in pyrochemical salt residues

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

Beta radiation effects in 137Cs-substituted pollucite

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

SHOW MORE ARTICLES

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

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

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

Conductivity of fission-damaged uranium nitride

Current status of SiC/SiC composites R&D

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

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

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

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

Destination of point defects and microstructural evolution under collision cascade damage

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

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

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