Nuclear Technology
Nuclear Technology is a journal indexed in SJR in Condensed Matter Physics and Nuclear Energy and Engineering with an H index of 65. It has an SJR impact factor of 0,531 and it has a best quartile of Q2. It is published in English. It has an SJR impact factor of 0,531.
Metrics
Scimago and CountryOfPapers database fields
SJR Impact
0,531
H-index
65
Docs (year)
252
Docs 3y
459
Total refs
7881
Cites 3y
805
Citable 3y
440
Cites/Doc 2y
1.52
Ref/Doc
31.27
Immediate OA
—
Embargoed OA
NPD
Non OA / Submission
—
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Researcher reviews
Best articles by citations
CFD Verification and Validation of Wire-Wrapped Pin Assemblies
View moreVIPRE-02 - A Two-Fluid Thermal-Hydraulics Code for Reactor Core and Vessel Analysis: Mathematical Modeling and Solution Methods
View moreEffectiveness of Model-Based Defenses for Digitally Controlled Industrial Systems: Nuclear Reactor Case Study
View moreDevelopment of a New Method for Simulating Gas-to-Particle Conversion During Sodium Pool Fires in SFR Containment
View moreDevelopment of a Compact Digital Reactivity Meter and a Reactor Physics Data Processor
View moreDevelopment of a Code with the Capability of Internal Assessment of Uncertainty
View moreDesign and Development of a Personal-Computer-Based Reactivity Meter for a Research Reactor
View moreCurrent Status of Knowledge of the Fluoride Salt (FLiNaK) Heat Transfer
View moreCore Materials Inventory and Behavior
View moreCore Designs and Economic Analyses of Homogeneous Thoria-Urania Fuel in Light Water Reactors
View moreContribution of Phenix to the Development of Transmutation Fuels and Targets in Sodium Fast Breeder Reactors
View moreCompatibility of Selected Ni-Based Alloys in Molten Li,Na,Be/F Salts with PuF3 and Tellurium Additions
View moreComparison of Characteristics of Solution and Conventional Reactors for 99Mo Production
View moreA Boiling Water Reactor in a Prestressed Reinforced Concrete Vessel for an Atomic Central Heating-and-Power Plant
View moreCalculation of Photon Exposure and Ambient Dose Slant-Path Buildup Factors for Radiological Assessment
View moreBayesian Radiation Source Localization
View moreAssessment of Homogeneous Thorium/Uranium Fuel for Pressurized Water Reactors
View moreAqueous Dissolution of Urania-Thoria Nuclear Fuel
View moreApplication of Radiogenic Lead with Dominant Content of208Pb for Long Prompt Neutron Lifetime in Fast Reactor
View moreAnalysis on Transmutation of Long-Lived Fission Product from the PWR Spent Fuel Using a 30-MW(thermal) RSG-GAS Reactor
View moreAnalysis of Loss-of-Flow Accidents for the NIST Research Reactor with Fuel Conversion from HEU to LEU
View moreAlternative Applications of Homogeneous Thoria-Urania Fuel in Light Water Reactors to Enhance the Economics of the Thorium Fuel Cycle
View moreAdvanced 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
View moreA Tomographic Method for Verification of the Integrity of Spent Nuclear Fuel Assemblies - II: Experimental Investigation
View more