ISSN: 0029-5450

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Nuclear Technology Q2 Unclaimed

Taylor and Francis Ltd. 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 57. It has an SJR impact factor of 0,665 and it has a best quartile of Q2. It is published in English. It has an SJR impact factor of 0,665.

Type: Journal

Type of Copyright:

Languages: English

Open Access Policy:

Type of publications:

Publication frecuency: -

Categories: Condensed Matter Physics (Q2) Nuclear and High Energy Physics (Q2) Nuclear Energy and Engineering (Q2)

Price

- €

Inmediate OA

NPD

Embargoed OA

- €

Non OA

Metrics

0,665

SJR Impact factor

57

H Index

151

Total Docs (Last Year)

443

Total Docs (3 years)

4192

Total Refs

603

Total Cites (3 years)

423

Citable Docs (3 years)

1.36

Cites/Doc (2 years)

27.76

Ref/Doc

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Aims and Scope

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

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

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

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

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

Bayesian Radiation Source Localization

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

The Critical Safety Functions and Plant Operation

Numerical Methodology to Evaluate Fast Reactor Sodium Combustion

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

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

SCALE 6: Comprehensive Nuclear Safety Analysis Code System

SHOW MORE ARTICLES

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

Aqueous Dissolution of Urania-Thoria Nuclear Fuel

Fabrication of Monolithic RERTR Fuels by Hot Isostatic Pressing

Leach Behavior of Hydrofracture Grout Incorporating Radioactive Wastes

Radiation Heat Transfer in the Molten Salt FLiNaK

Effects of Gamma Irradiation on Organic Membrane Materials

Assessment of Homogeneous Thorium/Uranium Fuel for Pressurized Water Reactors

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

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

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

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

Numerical Simulation of Sodium Pool Fire