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 2020-11-01 to 2024-11-01.)

Article	Citations
The Advancement of Neutron Shielding Materials for the Storage of Spent Nuclear Fuel	23
Multiobjective Core Reloading Pattern Optimization of PARR-1 Using Modified Genetic Algorithm Coupled with Monte Carlo Methods	18
Research on Simulation and State Prediction of Nuclear Power System Based on LSTM Neural Network	11
Multiple Assessments on the Gamma-Ray Protection Properties of Niobium-Doped Borotellurite Glasses: A Wide Range Investigation Using Monte Carlo Simulations	11
A New Precursor Integral Method for Solving Space-Dependent Kinetic Equations in Neutronic and Thermal-Hydraulic Coupling System	10
Effect of Thickness and Compaction Degree of Overburden Soil on Radon Reduction for Uranium Tailings Reservoir	9
The Investigation on Heat Transfer Characteristics of Steam Condensation in Presence of Noncondensable Gas under Natural Convection	8
An Efficient Scheme for Coupling OpenMC and FLUENT with Adaptive Load Balancing	8
Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation	7
The Research of Fault Diagnosis of Nuclear Power Plant Based on ELM-AdaBoost.SAMME	7
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall	6
A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants	6
Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump	6
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway	5
Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method	5
RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China	5
Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM	4
Reliability Assessment for a Safety-Related Digital Reactor Protection System Using Event-Tree/Fault-Tree (ET/FT) Method	4
Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library	4
COMSOL Simulation for Design of Induction Heating System in VULCAN Facility	4
Remaining Useful Life Prediction of Nuclear Power Machinery Based on an Exponential Degradation Model	4
Interim Storage of the Dalat Nuclear Research Reactor: Radiation Safety Analysis	4
Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response	4
Migration Simulation of Radioactive Soil Particles in the Atmospheric Environment Using CFD-DEM Coupled with Empirical Formulas	4
Studies on Optimal Strategy to Adopt Nuclear Power Plants into Saudi Arabian Energy System Using MESSAGE Tool	4

Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System	4
An Economic Cost Assessment on HALEU Fuels for Small Modular Reactors	4
Control Rod Modeling and Worth Calculation for a Typical 1100 MWe Nuclear Power Plant Using WIMS/D4 and CITATION	3
Nuclear Power Sustainability Path for China from the Perspective of Operations	3
Technical Options and Cost Estimates for Spent Nuclear Fuel Management at the Barakah Nuclear Power Plants	3
Public Health Effects of Radioactive Airborne Effluents from Nuclear and Coal-Fired Power Plant	3
Radiation Resistance of a Structural Material Based on Modified Titanium Hydride	3
Influence of Weak Compressibility on the Hydrodynamic Performance Evaluation of Pump Turbines in the Pump Mode	3
A Novel and High-Precision Method for Calculating the γ-Ray Build-Up Factor for Multilayer Shields	3
Numerical Investigation on Turbulent Flow and Heat Transfer of Helium-Xenon Gas Mixture in a Circular Tube	3
Manufacturing and Testing of an In Situ Stretching Sample Environment Equipment for Neutron Scattering Experiments	3
Xe Ion Irradiation-Induced Microstructural Evolution and Hardening Effect of Nickel-Base Superalloy	3
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method	3
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants	3
Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models	3
Mechanical Properties Evaluation and Crack Propagation Behavior in Dissimilar Metal Welded Joints of 304 L Austenitic Stainless Steel and SA508 Low-Alloy Steel	3
Power Level Control of Nuclear Power Plant Based on Asymptotical State Observer under Neutron Sensor Fault	3
Effectiveness of Serpentine Concrete as Shielding Material for Neutron Source Facility Using Monte Carlo Code	3
Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations	3
Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000	3
Simulation of Ionizing/Displacement Synergistic Effects on NPN Bipolar Transistors Irradiated by Mixed Neutrons and Gamma Rays	3