Science and Technology of Nuclear Installations
Science and Technology of Nuclear Installations is a journal indexed in SJR in Nuclear Energy and Engineering with an H index of 32. It is an CC BY Journal with a Single blind Peer Review review system, and It has a price of 1170 €. The scope of the journal is focused on nuclear installations, nuclear reactors, nuclear industry. It has an SJR impact factor of 0,322 and it has a best quartile of Q3. It is published in English. It has an SJR impact factor of 0,322.
Unclaimed profile — some fields may be incomplete.
Metrics
Campos Scimago / CoP — sin series inventadas
SJR Impact
0,322
H-index
32
Docs (year)
17
Docs 3y
137
Total refs
608
Cites 3y
167
Citable 3y
137
Cites/Doc 2y
1.07
Ref/Doc
35.76
Immediate OA
1170 €
Embargoed OA
NPD
Non OA / Submission
- €
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Researcher reviews
Best articles by citations
Assessment of LWR-HTR-GCFR Integrated Cycle
View moreValidation of Infinite Impulse Response Multilayer Perceptron for Modelling Nuclear Dynamics
View moreDelayed Station Blackout Event and Nuclear Safety
View moreDecay Heat Removal in GEN IV Gas-Cooled Fast Reactors
View moreConceptual Engineering of CARA Fuel Element with Negative Void Coefficient for Atucha II
View moreComparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code Systems
View moreCHF Enhancement of Advanced 37-Element Fuel Bundles
View moreCFD Simulation of Polydispersed Bubbly Two-Phase Flow around an Obstacle
View moreCFD Recombiner Modelling and Validation on the H2-Par and Kali-H2Experiments
View moreCFD Modeling of Wall Steam Condensation: Two-Phase Flow Approach versus Homogeneous Flow Approach
View moreCFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor
View moreCFD Analysis of a Slug Mixing Experiment Conducted on a VVER-1000 Model
View moreCalculations for a BWR Lattice with Adjacent Gadolinium Pins Using the Monte Carlo Cell Code Serpent v.1.1.7
View moreA Second-Order Turbulence Model Based on a Reynolds Stress Approach for Two-Phase Flow - Part I: Adiabatic Cases
View moreAssessment of an Isolation Condenser of an Integral Reactor in View of Uncertainties in Engineering Parameters
View moreApplication of REPAS Methodology to Assess the Reliability of Passive Safety Systems
View moreAnalysis of Wetting Characteristics on Microstructured Hydrophobic Surfaces for the Passive Containment Cooling System
View moreAnalysis of Steam Explosion under Conditions of Partially Flooded Cavity and Submerged Reactor Vessel
View moreAnalysis of Loss of Essential Power System Reported in Nuclear Power Plants
View moreAnalyses of the OSU-MASLWR Experimental Test Facility
View moreAnalyses of Instability Events in the Peach Bottom-2 BWR Using Thermal-Hydraulic and 3D Neutron Kinetic Coupled Codes Technique
View moreAn Overview of Westinghouse Realistic Large Break LOCA Evaluation Model
View moreAn Overview of the Pressurized Thermal Shock Issue in the Context of the NURESIM Project
View moreAn Enhanced Preventive Maintenance Optimization Model Based on a Three-Stage Failure Process
View more