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 2021-11-01 to 2025-11-01.)

Article	Citations
Investigation of Oxidation and Counter-Oxidation in a One-Quarter Circular Geometry due to Shadow Corrosion	16
Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions	13
Effect of Inhomogeneous Mechanical Properties on the Stress-Strain Field at the Crack Tip and Crack Growth Direction in Dissimilar Metal Welded Joints	10
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants	9
Study on Fuel Rod Melting and Molten Material Migration in Core Channels Based on Particle Method	8
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway	7
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
Technical Options and Cost Estimates for Spent Nuclear Fuel Management at the Barakah Nuclear Power Plants	6
Development of an Integrated Human Error Simulation Model in Nuclear Power Plant Decommissioning Activities	6
Rapid Determination of Gross Alpha/Beta Activity in Water Based on Reverse Osmosis Membrane Enrichment Pretreatment	6
Research on Channel Modeling and Communication Coverage of Wireless Sensor Networks in Barrier Area of Nuclear Power Plants	6
The Design and Analysis of Active–Passive Hybrid Vibration Isolation Mounts Applied in Pump	6
Detecting Unauthorized Movement of Radioactive Material Packages in Transport with an Adam-Optimized BP Neural Network Model	5
Nuclear Waste Management: A Mini Review on Waste Package Characterization Approaches	5
Evaluation of Worker Radiation Exposure during the Kori Unit 1 Steam Generator Dismantling Process	5
A Data-Driven Fault Prediction Method for Nuclear Power Systems Based on End-to-End Deep Learning Framework	4
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 Arrays	4
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger	4
Mechanical Properties Evaluation and Crack Propagation Behavior in Dissimilar Metal Welded Joints of 304 L Austenitic Stainless Steel and SA508 Low-Alloy Steel	4
Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA	4
Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump	4
Prediction of Automatic Scram during Abnormal Conditions of Nuclear Power Plants Based on Long Short-Term Memory (LSTM) and Dropout	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
Control Rod Modeling and Worth Calculation for a Typical 1100 MWe Nuclear Power Plant Using WIMS/D4 and CITATION	3
Machine Learning-Based Approach for Hydrogen Economic Evaluation of Small Modular Reactors	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
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
Research on Radionuclide Diffusion Mechanism in the Ocean and Emergency Response under Oceanic Radioactive Events	3
Interaction of Mechanical Heterogeneity and Residual Stress on Mechanical Field at Crack Tips in DMWJs	3
Assessment of Computational Technicalities for 2D/1D Coupling Method and Its Comparison with 3D MOC	3
Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations	3
Accident Sequence Precursor Analysis of an Incident in a Japanese Nuclear Power Plant Based on Dynamic Probabilistic Risk Assessment	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
Effect of Chloride Ions on Electrochemical Behavior of Canister Materials	3
A Reduced Order Model Based on ANN-POD Algorithm for Steady-State Neutronics and Thermal-Hydraulics Coupling Problem	2
Assessing the Impact of Common Cause Failures on Site Risk within Level 1 Multi-Unit PSA	2
Methods for Predicting the Minimum Temperature of the Outage Loop and the Maximum Power Caused by the Low-Temperature Coolant	2
Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation	2
Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM	2
Design Change and Operational Consideration of the HVAC System during Nuclear Power Plant Decommissioning	2
Verification of the Efficacy of Passive Autocatalytic Recombiners in a Typical Pressurized Water Reactor under a Station Blackout Condition	2
Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel	2
Analysis of the Effect of Applied Load on Crevice Corrosion Behavior	2
Quantitative Assessment of Gaseous Effluents during Routine Operation: A Comparative Study of Planned Nuclear Power Plants at Lubiatowo‐Kopalino and Pątnów Sites in Poland	2
Study on the Applicability of Neutron Radiation Damage Method Used for High-Temperature Superconducting Tape Based on Geant4 and SRIM	2
Pressurized Water Reactor Transient Detection With Artificial Intelligence to Support Reactor Operators	2
High-Temperature Corrosion Behavior of Incoloy 800H Alloy in the Impure Helium Environment	2
Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System	2
The Concept of the Heat Removal System of a High-Flux Research Reactor	2
	2
Deep Learning–Based Fault Identification Testing Experiment for Bellows Valves	1
A Novel Transformer‐Based Anomaly Detection Model for the Reactor Coolant Pump in Nuclear Power Plants	1
Uranium Recovery from Phosphates for Self-Sufficient Nuclear Power in the Eastern Mediterranean	1
Study on Missing Data Filling Algorithm of Nuclear Power Plant Operation Parameters	1
Solution of the Static Deflection Mode Shape Function of the Cantilever Beam under Transverse Flow Based on the Boundary Shooting Method	1
Design of Control System of Once-Through Steam Generator Based on Proximal Policy Optimization Algorithm	1
Effect of Photomultiplier Tube Voltage on the Performance of Sealed NaI (Tl) Scintillator Detectors	1
Application of EDG AOT Extension Based on the Risk-Informed Method in NPPs	1
Nuclear Power Sustainability Path for China from the Perspective of Operations	1
Analysis of Heat Release Processes inside Storage Facilities Containing Irradiated Nuclear Graphite	1
Advancing Small Modular Reactor Technology Assessment in the Czech Republic, Egypt, and Poland	1
Simulation of Ionizing/Displacement Synergistic Effects on NPN Bipolar Transistors Irradiated by Mixed Neutrons and Gamma Rays	1
Oceanic Radionuclide Dispersion Method Investigation for Nonfixed Source from Marine Reactor Accident	1
Innovative Design of Compact Heavy-Load Independent Transfer Device for Nuclear Engineering System	1
Study on the Dispersion of Radionuclides under Different Hydrological Conditions of Spent Fuel Shipping in Daya Bay	1
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall	1
Acceptable Level of Acceptance and the Affecting Factors: What Is the Acceptable Public Acceptance of Building a Nuclear Power Plant	1
Preliminary Study on Risk Identification and Assessment Framework for Fusion Radioactive Waste Management	1
Effectiveness of Serpentine Concrete as Shielding Material for Neutron Source Facility Using Monte Carlo Code	1
Logistical Simulation for Blending of Concrete Waste in Kori‐1 NPP Decommissioning	1

	1
Research and Analysis on Assembly Methodology for the Fusion Blanket System	1
Influence of Weak Compressibility on the Hydrodynamic Performance Evaluation of Pump Turbines in the Pump Mode	1