verified SJR 0,984 · Q1 • database Scopus / SJR & Web of Science indexed

Netherlands · Elsevier B.V.

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Journal of Nuclear Materials

Journal of Nuclear Materials is a journal indexed in SJR in Materials Science (miscellaneous) and Nuclear Energy and Engineering with an H index of 174. It has an SJR impact factor of 0,984 and it has a best quartile of Q1. It is published in English. It has an SJR impact factor of 0,984.

Journal of Nuclear Materials focuses its scope in these topics and keywords: oxide, steel, tungsten, americium, charged, cascades, control, coupled, isostatic, neutroninduced, ...

ISSN: 0022-3115

Editorial: Elsevier B.V.

Category: Materials Science (miscellaneous)

Indexation: verifiedScopus / SJR verifiedWeb of Science

Unclaimed profile — some fields may be incomplete.

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SJR Impact Factor trending_up

0,984 Q1

H-index 174

Tasa de Aceptación pie_chart

22% Selectiva

Fuente Acceptance_Rate

Tiempo a publicación hourglass_top

NPD

Campo Sin dato

Coste de Publicación (APC) payments

NPD Subscription

Ruta Non-OA NPD

Metrics

Campos Scimago / CoP — sin series inventadas

Scopus / SJR Web of Science

SJR Impact

0,984

H-index

174

Docs (year)

485

Docs 3y

1794

Total refs

24596

Cites 3y

6019

Citable 3y

1781

Cites/Doc 2y

3.19

Ref/Doc

50.71

Immediate OA

—

Embargoed OA

NPD

Non OA / Submission

—

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Best articles by citations

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

Zirconium oxidation at low temperature and pressure (Comments on a paper by X. Iltis et al., J. Nucl. Mater. 209 (1994) 180)

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

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

Destination of point defects and microstructural evolution under collision cascade damage

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

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

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

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

Current status of SiC/SiC composites R&D

Conductivity of fission-damaged uranium nitride

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

SHOW MORE ARTICLES

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

A fast scanning Langmuir probe system for ASDEX-Upgrade divertor

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

Beta radiation effects in 137Cs-substituted pollucite

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

Analysis and characterization of plutonium in pyrochemical salt residues

An unified model of steady-state segregation in multicomponent alloys

Activation of stainless steel with high energy neutrons

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

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

A novel technique to remove deuterium from CANDU pressure tubes

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

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