Default: Journal of Nuclear Materials

ISSN: 0022-3115

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Journal of Nuclear Materials Q1 Unclaimed

Elsevier Netherlands
Unfortunately this journal has not been claimed yet. For this reason, some information may be unavailable.

Journal of Nuclear Materials is a journal indexed in SJR in Materials Science (miscellaneous) and Nuclear Energy and Engineering with an H index of 141. It has an SJR impact factor of 1,123 and it has a best quartile of Q1. It is published in English. It has an SJR impact factor of 1,123.

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: -

Metrics

Journal of Nuclear Materials

1,123

SJR Impact factor

141

H Index

555

Total Docs (Last Year)

1854

Total Docs (3 years)

25132

Total Refs

5611

Total Cites (3 years)

1843

Citable Docs (3 years)

3,00

Cites/Doc (2 years)

45,28

Ref/Doc

Aims and Scope


americium, tungsten, steel, oxide, driven, displacement, extruded, fuel, carboncontaining, generate, equations, hot, ii, injected, interstitial, investigation, irradiated, irradiationcorrosion, isostatic, dispersion, dioxide, defect, annealing, carlo, cascade, cascades, ceramic, charged, control, correlation, coupled, creep, csionsiv, cubic, damageinstability,



Best articles by citations

Beta radiation effects in 137Cs-substituted pollucite

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Analysis and characterization of plutonium in pyrochemical salt residues

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Simulation of CsI decomposition in fuel cladding gap

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

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High temperature steam oxidation of U02 fuel pellets

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

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

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Conductivity of fission-damaged uranium nitride

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Hardening of Alloy N10276 by diluted flowing butane gas

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Dynamic behavior of hydrogen atoms with a boronized wall

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

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

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Enthalpies of formation of CeNi2 and CeNi5 by calorimetry

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

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Edge localised asymmetric radiative phenomena in RFX

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Solid state reactions of uranium oxides with ammonium sulphate

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

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

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Edge plasma modeling of limiter surfaces in a tokamak divertor configuration

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Numerical analysis of thermoelectric instability in tokamak divertor

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Edge profiles and limiter tests in Extrap T2

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

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

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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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