OOIR: Observatory of International Research

Papers

(The TQCC of Science and Technology of Nuclear Installations is 2. 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 2020-03-01 to 2024-03-01.)

Article	Citations
The Influence of Radiation on Confinement Properties of Nuclear Waste Glasses	23
The Advancement of Neutron Shielding Materials for the Storage of Spent Nuclear Fuel	20
Multiobjective Core Reloading Pattern Optimization of PARR-1 Using Modified Genetic Algorithm Coupled with Monte Carlo Methods	16
Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core	15
Emission of Noble Gases Binary Mixtures under Excitation by the Products of the ⁶Li (n, α)³ H Nuclear Reaction	12
Research on Simulation and State Prediction of Nuclear Power System Based on LSTM Neural Network	11
A New Precursor Integral Method for Solving Space-Dependent Kinetic Equations in Neutronic and Thermal-Hydraulic Coupling System	10
Review on Selection and Experiment Method of Commonly Studied Simulated Radionuclides in Researches of Nuclear Waste Solidification	9
Effect of Thickness and Compaction Degree of Overburden Soil on Radon Reduction for Uranium Tailings Reservoir	8
An Efficient Scheme for Coupling OpenMC and FLUENT with Adaptive Load Balancing	7
Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled Neutronics/Thermal-Hydraulics Simulations	6
Multiple Assessments on the Gamma-Ray Protection Properties of Niobium-Doped Borotellurite Glasses: A Wide Range Investigation Using Monte Carlo Simulations	6
Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation	6
Best-Estimate Plus Uncertainty Framework for Multiscale, Multiphysics Light Water Reactor Core Analysis	5
Transient Study on the HTR-PM with TINTE-vPower Coupling Code Package	5
Conceptual Design of a 10 MW Multipurpose Research Reactor Using VVR-KN Fuel	5
Studies on Optimal Strategy to Adopt Nuclear Power Plants into Saudi Arabian Energy System Using MESSAGE Tool	4
Bubble Bursting and Drainage Characteristics at the Free Surface of a Liquid Pool with an Aerosol	4
RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China	4
Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump	4
A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants	4
Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors	4
Remaining Useful Life Prediction Techniques of Electric Valves for Nuclear Power Plants with Convolution Kernel and LSTM	4
Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method	4
Monte Carlo Simulation and Experimental Validation for Radiation Protection with Multiple Complex Source Terms and Deep Penetration for a Radioactive Liquid Waste Cementation Facility	4

Reliability Assessment for a Safety-Related Digital Reactor Protection System Using Event-Tree/Fault-Tree (ET/FT) Method	4
Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations	4
An Economic Cost Assessment on HALEU Fuels for Small Modular Reactors	4
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall	4
Migration Simulation of Radioactive Soil Particles in the Atmospheric Environment Using CFD-DEM Coupled with Empirical Formulas	4
Studies on Key Effect Factors of Natural Circulation Characteristics for Advanced PWR Reactor Cavity Flooding System	3
The Research of Fault Diagnosis of Nuclear Power Plant Based on ELM-AdaBoost.SAMME	3
Development and Validation of Rapid 3D Radiation Field Evaluation Technique for Nuclear Power Plants	3
Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response	3
COMSOL Simulation for Design of Induction Heating System in VULCAN Facility	3
Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM	3
Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System	3
Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library	3
A Novel and High-Precision Method for Calculating the γ-Ray Build-Up Factor for Multilayer Shields	3
Public Health Effects of Radioactive Airborne Effluents from Nuclear and Coal-Fired Power Plant	3
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method	3
Source Term Derivation and Radioactive Release Evaluation for JRTR Research Reactor under Severe Accident	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
Radiation Resistance of a Structural Material Based on Modified Titanium Hydride	2
Influence of Weak Compressibility on the Hydrodynamic Performance Evaluation of Pump Turbines in the Pump Mode	2
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants	2
Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART	2
Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions	2
Power Level Control of Nuclear Power Plant Based on Asymptotical State Observer under Neutron Sensor Fault	2
Steady-State Thermal-Hydraulic Analysis of the LEU-Fueled Dalat Nuclear Research Reactor	2
Vehicle Transport Security System Based on the Self-Security Intelligence of Radioactive Material	2
Interim Storage of the Dalat Nuclear Research Reactor: Radiation Safety Analysis	2
Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000	2
Simulation of Ionizing/Displacement Synergistic Effects on NPN Bipolar Transistors Irradiated by Mixed Neutrons and Gamma Rays	2
Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models	2
Control Rod Modeling and Worth Calculation for a Typical 1100 MWe Nuclear Power Plant Using WIMS/D4 and CITATION	2
Theoretical Study on the Characteristics of Critical Heat Flux in Rectangular Channel of Natural Circulation under Motion Conditions	2
Effect of Chloride Ions on Electrochemical Behavior of Canister Materials	2
The Investigation on Heat Transfer Characteristics of Steam Condensation in Presence of Noncondensable Gas under Natural Convection	2
Manufacturing and Testing of an In Situ Stretching Sample Environment Equipment for Neutron Scattering Experiments	2
Xe Ion Irradiation-Induced Microstructural Evolution and Hardening Effect of Nickel-Base Superalloy	2
Innovative Design of Compact Heavy-Load Independent Transfer Device for Nuclear Engineering System	2
Nonlinear Seismic Response Characteristics of CAP1400 Nuclear Island Structure on Soft Rock Sites	2
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway	2
Single-Vehicle Transportation Security System of Radioactive Materials Based on Group Relationship to Prevent Loss and Theft	2
Numerical Investigation on Turbulent Flow and Heat Transfer of Helium-Xenon Gas Mixture in a Circular Tube	2
Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 1	2
Numerical Investigation of Water Film Evaporation with the Countercurrent Air in the Asymmetric Heating Rectangular Channel for Passive Containment Cooling System	2
Remaining Useful Life Prediction of Nuclear Power Machinery Based on an Exponential Degradation Model	2
Study on the Sensitivity and Uncertainty of Nuclear Data to the Sodium-Cooled Linear Breed-and-Burn Fast Reactor Using SCALE6.2 Code	2
Uranium Decontamination from Waste Soils by Chlorination with ZrCl4 in LiCl-KCl Eutectic Salt	2