OOIR: Observatory of International Research

Papers

(The TQCC of Science and Technology of Nuclear Installations is 3. 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 2022-06-01 to 2026-06-01.)

Article	Citations
Investigation of Oxidation and Counter-Oxidation in a One-Quarter Circular Geometry due to Shadow Corrosion	31
Vacuum Analysis and Experiment of Free‐Electron Laser Oscillator Based on Molflow+ Simulation	15
Effect of Inhomogeneous Mechanical Properties on the Stress-Strain Field at the Crack Tip and Crack Growth Direction in Dissimilar Metal Welded Joints	11
Implications of Innovative Nuclear Technologies on Ghana’s Nuclear Future	10
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway	10
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants	10
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method	8
Research on Optimization of Roof Shielding Design for Radioactive Waste Temporary Storage Facilities	8
Study on Fuel Rod Melting and Molten Material Migration in Core Channels Based on Particle Method	8
The Design and Analysis of Active–Passive Hybrid Vibration Isolation Mounts Applied in Pump	7
Development of an Integrated Human Error Simulation Model in Nuclear Power Plant Decommissioning Activities	7
	7
Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library	7
Improvement of the Power Supply Technical Scheme for the Electric Melter System in High‐Level Radioactive Liquid Waste Vitrification	5
Nuclear Waste Management: A Mini Review on Waste Package Characterization Approaches	5
Prediction of Crack Propagation Directions in Dissimilar Metal‐Welded Joints Using Phase‐Field Models and Discussion of Its Mechanisms	4
Optimization of the n / γ Pulse Shape Discrimination Performance of Plastic Scintillator Coupled With SiPM	4
A Data-Driven Fault Prediction Method for Nuclear Power Systems Based on End-to-End Deep Learning Framework	4
Correction to “Count Loss Evaluation for Accuracy Enhancement of a FPGA‐Based Gamma Spectroscopy”	4
Evaluation of Worker Radiation Exposure during the Kori Unit 1 Steam Generator Dismantling Process	4
Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA	4
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger	4
Detecting Unauthorized Movement of Radioactive Material Packages in Transport with an Adam-Optimized BP Neural Network Model	4
An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes	3
Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations	3

Effect of Chloride Ions on Electrochemical Behavior of Canister Materials	3
Research on Radionuclide Diffusion Mechanism in the Ocean and Emergency Response under Oceanic Radioactive Events	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
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	3
Accident Sequence Precursor Analysis of an Incident in a Japanese Nuclear Power Plant Based on Dynamic Probabilistic Risk Assessment	3
Enhancing Radiation Shielding with Gadolinium(III) Oxide in Cerium(III) Fluoride‐Doped Silica Borate Glass	3
Exponential Response Matrix Spectral Nodal Method for the Discrete Ordinates Neutral Particle Transport Model	3
The Study of Dosimetric Characteristics of the XHA600D Medical Linear Accelerator Based on a Monte Carlo Code	3
Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material	3