OOIR: Observatory of International Research

Papers

(The median citation count of Science and Technology of Nuclear Installations is 1. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2022-08-01 to 2026-08-01.)

Article	Citations
Investigation of Oxidation and Counter-Oxidation in a One-Quarter Circular Geometry due to Shadow Corrosion	41
Vacuum Analysis and Experiment of Free‐Electron Laser Oscillator Based on Molflow+ Simulation	16
Implications of Innovative Nuclear Technologies on Ghana’s Nuclear Future	11
Effect of Inhomogeneous Mechanical Properties on the Stress-Strain Field at the Crack Tip and Crack Growth Direction in Dissimilar Metal Welded Joints	11
Study on Fuel Rod Melting and Molten Material Migration in Core Channels Based on Particle Method	10
Research on Optimization of Roof Shielding Design for Radioactive Waste Temporary Storage Facilities	10
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method	9
Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library	8
Development of an Integrated Human Error Simulation Model in Nuclear Power Plant Decommissioning Activities	8
CFD‐Based Analysis of Petrochemical Hazard Dispersion Under Mountain Barrier Effect: Impacts on the Safety of Nuclear Steam Supply Plants	7
The Design and Analysis of Active–Passive Hybrid Vibration Isolation Mounts Applied in Pump	7
	4
Evaluation of Worker Radiation Exposure during the Kori Unit 1 Steam Generator Dismantling Process	4
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger	4
Nuclear Waste Management: A Mini Review on Waste Package Characterization Approaches	4
Improvement of the Power Supply Technical Scheme for the Electric Melter System in High‐Level Radioactive Liquid Waste Vitrification	4
Optimization of the n / γ Pulse Shape Discrimination Performance of Plastic Scintillator Coupled With SiPM	4
Detecting Unauthorized Movement of Radioactive Material Packages in Transport with an Adam-Optimized BP Neural Network Model	4
Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA	4
Prediction of Crack Propagation Directions in Dissimilar Metal‐Welded Joints Using Phase‐Field Models and Discussion of Its Mechanisms	3
Prediction of Automatic Scram during Abnormal Conditions of Nuclear Power Plants Based on Long Short-Term Memory (LSTM) and Dropout	3
Assessment of Computational Technicalities for 2D/1D Coupling Method and Its Comparison with 3D MOC	3
A Hybrid Method to Predict the Remaining Useful Life of Scroll Wheel of Control Rod Drive Mechanism	3
A Data-Driven Fault Prediction Method for Nuclear Power Systems Based on End-to-End Deep Learning Framework	3
Enhancing Radiation Shielding with Gadolinium(III) Oxide in Cerium(III) Fluoride‐Doped Silica Borate Glass	3

Effect of Chloride Ions on Electrochemical Behavior of Canister Materials	3
The Study of Dosimetric Characteristics of the XHA600D Medical Linear Accelerator Based on a Monte Carlo Code	3
Correction to “Count Loss Evaluation for Accuracy Enhancement of a FPGA‐Based Gamma Spectroscopy”	3
Accident Sequence Precursor Analysis of an Incident in a Japanese Nuclear Power Plant Based on Dynamic Probabilistic Risk Assessment	3
Exponential Response Matrix Spectral Nodal Method for the Discrete Ordinates Neutral Particle Transport Model	3
Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material	3
Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations	3
Methods for Predicting the Minimum Temperature of the Outage Loop and the Maximum Power Caused by the Low-Temperature Coolant	2
Machine Learning-Based Approach for Hydrogen Economic Evaluation of Small Modular Reactors	2
Assessing the Impact of Common Cause Failures on Site Risk within Level 1 Multi-Unit PSA	2
Research on Radionuclide Diffusion Mechanism in the Ocean and Emergency Response under Oceanic Radioactive Events	2
A Systematic Framework for Risk Assessment of Fusion Blanket: Addressing Manufacturing Defects, Accident Scenarios, and Radioactive Release	2
Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation	2
High-Temperature Corrosion Behavior of Incoloy 800H Alloy in the Impure Helium Environment	2
Accuracy Evaluation of Monte Carlo Simulation Results Using ENDF/B‐VIII.0 and JENDL‐5 Libraries for 10 MW_th Micro Heat Pipe‐Cooled Reactor	2
Analysis of the Effect of Applied Load on Crevice Corrosion Behavior	2
CFD‐Assisted Spray Decontamination Process Assessment for Nuclear Tank Decommissioning	2
Nuclear Power Sustainability Path for China from the Perspective of Operations	1
Analysis With Different Containment Models for Containment Response of NHR200II Under Loss‐of‐Coolant Accident	1
Deep Learning–Based Fault Identification Testing Experiment for Bellows Valves	1
Design Change and Operational Consideration of the HVAC System during Nuclear Power Plant Decommissioning	1
A Reduced Order Model Based on ANN-POD Algorithm for Steady-State Neutronics and Thermal-Hydraulics Coupling Problem	1
Transmuting the Arid: Fission‐Powered Visions—Unlocking Ghana’s Aquatic Destiny Through Nuclear Desalination	1
Pressurized Water Reactor Transient Detection With Artificial Intelligence to Support Reactor Operators	1
Natural Convection Heat Transfer Analysis With Different DHX Operation Conditions of Sodium‐Cooled Fast Reactor Using ATHLET Code	1
Acceptable Level of Acceptance and the Affecting Factors: What Is the Acceptable Public Acceptance of Building a Nuclear Power Plant	1
Application of EDG AOT Extension Based on the Risk-Informed Method in NPPs	1
Alternate Method for Calibration of PRDs by Means of Gamma Radiation Emitted by Radionuclides	1
	1
Quantitative Assessment of Gaseous Effluents during Routine Operation: A Comparative Study of Planned Nuclear Power Plants at Lubiatowo‐Kopalino and Pątnów Sites in Poland	1
Numerical Simulation of UF ₄ Erosion Behaviors in Fluorination Furnace	1
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall	1