ISSN: 1687-6075

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Science and Technology of Nuclear Installations Q2 Unclaimed

Hindawi Limited Egypt

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Science and Technology of Nuclear Installations is a journal indexed in SJR in Nuclear Energy and Engineering with an H index of 29. 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 0,381 and it has a best quartile of Q2. It is published in English. It has an SJR impact factor of 0,381.

Type: Journal

Type of Copyright: CC BY

Languages: English

Open Access Policy: Open Access

Type of publications:

Publication frecuency: -

Categories: Nuclear Energy and Engineering (Q2)

Price

1170 €

Inmediate OA

NPD

Embargoed OA

- €

Non OA

Metrics

Science and Technology of Nuclear Installations

0,381

SJR Impact factor

29

H Index

21

Total Docs (Last Year)

165

Total Docs (3 years)

545

Total Refs

207

Total Cites (3 years)

165

Citable Docs (3 years)

1.09

Cites/Doc (2 years)

25.95

Ref/Doc

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Aims and Scope

Nuclear installations Nuclear reactors Nuclear industry

Best articles by citations

Review on Recent Developments in Laser Driven Inertial Fusion

Comparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code Systems

Calculations for a BWR Lattice with Adjacent Gadolinium Pins Using the Monte Carlo Cell Code Serpent v.1.1.7

Heat Transfer Analysis of Passive Residual Heat Removal Heat Exchanger under Natural Convection Condition in Tank

Assessment of an Isolation Condenser of an Integral Reactor in View of Uncertainties in Engineering Parameters

Uncertainty and Sensitivity of Neutron Kinetic Parameters in the Dynamic Response of a PWR Rod Ejection Accident Coupled Simulation

Single Phase Natural Circulation Behaviors of the Integral Type Marine Reactor Simulator under Rolling Motion Condition

CFD Analysis of a Slug Mixing Experiment Conducted on a VVER-1000 Model

Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor

CFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor

Radiogenic Lead with Dominant Content of208Pb: New Coolant and Neutron Moderator for Innovative Nuclear Facilities

The Verification of Coupled Neutronics Thermal-Hydraulics Code NODAL3 in the PWR Rod Ejection Benchmark

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Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor

Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code

Non-Boussinesq Integral Model for Horizontal Turbulent Buoyant Round Jets

An Enhanced Preventive Maintenance Optimization Model Based on a Three-Stage Failure Process

Study on the Use of Hydride Fuel in High-Performance Light Water Reactor Concept

CFD Modeling of Wall Steam Condensation: Two-Phase Flow Approach versus Homogeneous Flow Approach

Study on Thermal-Hydraulic Behavior of an Integral Type Reactor under Heaving Condition

The Influence of the Packing Factor on the Fuel Temperature Hot Spots in a Particle-Bed GCFR

CFD Recombiner Modelling and Validation on the H2-Par and Kali-H2Experiments

Analyses of Instability Events in the Peach Bottom-2 BWR Using Thermal-Hydraulic and 3D Neutron Kinetic Coupled Codes Technique

Simulation of the Thermal Conditions of Cask with Fuel Assemblies of BN-350 Reactor for Dry Storage

Simulation of the Thermal Hydraulic Processes in the Horizontal Steam Generator with the Use of the Different Interfacial Friction Correlations