Default: Journal of Nuclear Materials

ISSN: 0022-3115

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Journal of Nuclear Materials Q1 Unclaimed

Elsevier B.V. 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 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: -

Metrics

Journal of Nuclear Materials

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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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,



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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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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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