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 2022-05-01 to 2026-05-01.)

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
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants	10
Implications of Innovative Nuclear Technologies on Ghana’s Nuclear Future	9
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway	9
Study on Fuel Rod Melting and Molten Material Migration in Core Channels Based on Particle Method	8
Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library	7
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method	7
Development of an Integrated Human Error Simulation Model in Nuclear Power Plant Decommissioning Activities	7
Research on Optimization of Roof Shielding Design for Radioactive Waste Temporary Storage Facilities	7
The Design and Analysis of Active–Passive Hybrid Vibration Isolation Mounts Applied in Pump	6
	6
Improvement of the Power Supply Technical Scheme for the Electric Melter System in High‐Level Radioactive Liquid Waste Vitrification	6
Evaluation of Worker Radiation Exposure during the Kori Unit 1 Steam Generator Dismantling Process	5
Nuclear Waste Management: A Mini Review on Waste Package Characterization Approaches	5
Detecting Unauthorized Movement of Radioactive Material Packages in Transport with an Adam-Optimized BP Neural Network Model	4
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger	4
A Data-Driven Fault Prediction Method for Nuclear Power Systems Based on End-to-End Deep Learning Framework	4
Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump	4
Optimization of the n / γ Pulse Shape Discrimination Performance of Plastic Scintillator Coupled With SiPM	4
Accident Sequence Precursor Analysis of an Incident in a Japanese Nuclear Power Plant Based on Dynamic Probabilistic Risk Assessment	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	4
Correction to “Count Loss Evaluation for Accuracy Enhancement of a FPGA‐Based Gamma Spectroscopy”	4

Enhancing Radiation Shielding with Gadolinium(III) Oxide in Cerium(III) Fluoride‐Doped Silica Borate Glass	3
The Study of Dosimetric Characteristics of the XHA600D Medical Linear Accelerator Based on a Monte Carlo Code	3
Prediction of Automatic Scram during Abnormal Conditions of Nuclear Power Plants Based on Long Short-Term Memory (LSTM) and Dropout	3
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
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
Exponential Response Matrix Spectral Nodal Method for the Discrete Ordinates Neutral Particle Transport Model	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
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