ISSN: 0022-3115

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Journal of Nuclear Materials Q1 Unclaimed

Elsevier B.V. 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 166. It has an SJR impact factor of 0,923 and it has a best quartile of Q1. It is published in English. It has an SJR impact factor of 0,923.

Journal of Nuclear Materials focuses its scope in these topics and keywords: americium, tungsten, steel, oxide, driven, displacement, extruded, fuel, carboncontaining, generate, ...

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

- €

Inmediate OA

NPD

Embargoed OA

- €

Non OA

Metrics

0,923

SJR Impact factor

166

H Index

531

Total Docs (Last Year)

1825

Total Docs (3 years)

26758

Total Refs

5818

Total Cites (3 years)

1816

Citable Docs (3 years)

3.1

Cites/Doc (2 years)

50.39

Ref/Doc

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Annual Review of Condensed Matter Physics Q1
Advanced Materials Q1
Advanced Energy Materials Q1
Progress in Materials Science Q1
Materials Science and Engineering: R: Reports Q1

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Aims and Scope

Best articles by citations

Beta radiation effects in 137Cs-substituted pollucite

Analysis and characterization of plutonium in pyrochemical salt residues

Simulation of CsI decomposition in fuel cladding gap

The disappearance of voids during 180 keV Ni+ bombardment of nickel

High temperature steam oxidation of U02 fuel pellets

Radiation embrittlement of Mo-Re welds under low-temperature irradiation in the SM reactor

The reaction of liquid sodium with the oxides CeO2 and Ce2O3 and the determination of the free energy of formation of NaCeO2 and Na2CeO3

Conductivity of fission-damaged uranium nitride

Hardening of Alloy N10276 by diluted flowing butane gas

Dynamic behavior of hydrogen atoms with a boronized wall

Influence of prior thermal ageing on tensile deformation and fracture behaviour of forged thick section 9Cr-1Mo ferritic steel

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

SHOW MORE ARTICLES

Enthalpies of formation of CeNi2 and CeNi5 by calorimetry

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

Edge localised asymmetric radiative phenomena in RFX

Solid state reactions of uranium oxides with ammonium sulphate

Reduction of the open porosity of UO2 pellets through pore structure control

Time variation of the optical absorption of quartz KU-1 induced by gamma irradiation

Edge plasma modeling of limiter surfaces in a tokamak divertor configuration

Numerical analysis of thermoelectric instability in tokamak divertor

Edge profiles and limiter tests in Extrap T2

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

Quantitative analysis of deuterium in a-C:D layers, a Round Robin experiment

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