Default: Nuclear Technology

ISSN: 0029-5450

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Nuclear Technology Q2 Unclaimed

American Nuclear Society United States
Unfortunately this journal has not been claimed yet. For this reason, some information may be unavailable.

Nuclear Technology is a journal indexed in SJR in Condensed Matter Physics and Nuclear Energy and Engineering with an H index of 50. It has an SJR impact factor of 0,736 and it has a best quartile of Q2. It is published in English. It has an SJR impact factor of 0,736.

Type: Journal

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Languages: English

Open Access Policy:

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Nuclear Technology


SJR Impact factor


H Index


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Total Docs (3 years)


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Total Cites (3 years)


Citable Docs (3 years)


Cites/Doc (2 years)




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Best articles by citations

Advanced MCNP Simulation of the Neutron and Photon Flux and Absorbed Dose Rates for the SLOWPOKE-2 Nuclear Reactor at the Royal Military College of Canada

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Evaluation of the Fluid-Structure Interaction Effects in a Lead-Cooled Fast Reactor

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Studies of the Preparation of Thoria and Thoria-Urania Microspheres Using an Internal Gelation Process

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The Probability of Liner Failure in a Mark-I Containment, Part I: Probabilistic Framework and Results

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Implications of Plutonium Isotopic Separation on Closed Fuel Cycles and Repository Design

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Bayesian Radiation Source Localization

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Effectiveness of Model-Based Defenses for Digitally Controlled Industrial Systems: Nuclear Reactor Case Study

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The Critical Safety Functions and Plant Operation

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Numerical Methodology to Evaluate Fast Reactor Sodium Combustion

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Investigation of Effect of Ballooned Fuel Pins on Quenching Behavior: Design of Experiment and Preliminary Analysis

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A Tomographic Method for Verification of the Integrity of Spent Nuclear Fuel Assemblies - II: Experimental Investigation

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SCALE 6: Comprehensive Nuclear Safety Analysis Code System

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Application of Radiogenic Lead with Dominant Content of208Pb for Long Prompt Neutron Lifetime in Fast Reactor

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Aqueous Dissolution of Urania-Thoria Nuclear Fuel

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Fabrication of Monolithic RERTR Fuels by Hot Isostatic Pressing

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Leach Behavior of Hydrofracture Grout Incorporating Radioactive Wastes

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Radiation Heat Transfer in the Molten Salt FLiNaK

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Effects of Gamma Irradiation on Organic Membrane Materials

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New Approach for Fatigue Damage Monitoring Based on Actual Operating History of Nuclear Power Plants

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On the Solution of the Nonlinear Fractional Neutron Point-Kinetics Equation with Newtonian Temperature Feedback Reactivity

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Compatibility of Selected Ni-Based Alloys in Molten Li,Na,Be/F Salts with PuF3 and Tellurium Additions

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Analysis on Transmutation of Long-Lived Fission Product from the PWR Spent Fuel Using a 30-MW(thermal) RSG-GAS Reactor

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