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 2020-05-01 to 2024-05-01.)

Article	Citations
The Influence of Radiation on Confinement Properties of Nuclear Waste Glasses	22
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	16
Research on Simulation and State Prediction of Nuclear Power System Based on LSTM Neural Network	12
Emission of Noble Gases Binary Mixtures under Excitation by the Products of the ⁶Li (n, α)³ H Nuclear Reaction	12
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
Review on Selection and Experiment Method of Commonly Studied Simulated Radionuclides in Researches of Nuclear Waste Solidification	8
Multiple Assessments on the Gamma-Ray Protection Properties of Niobium-Doped Borotellurite Glasses: A Wide Range Investigation Using Monte Carlo Simulations	8
An Efficient Scheme for Coupling OpenMC and FLUENT with Adaptive Load Balancing	7
Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation	7
Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled Neutronics/Thermal-Hydraulics Simulations	6
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall	6
The Investigation on Heat Transfer Characteristics of Steam Condensation in Presence of Noncondensable Gas under Natural Convection	5
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
Bubble Bursting and Drainage Characteristics at the Free Surface of a Liquid Pool with an Aerosol	4
An Economic Cost Assessment on HALEU Fuels for Small Modular Reactors	4
Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method	4
Reliability Assessment for a Safety-Related Digital Reactor Protection System Using Event-Tree/Fault-Tree (ET/FT) Method	4
Remaining Useful Life Prediction Techniques of Electric Valves for Nuclear Power Plants with Convolution Kernel and LSTM	4
Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump	4
Migration Simulation of Radioactive Soil Particles in the Atmospheric Environment Using CFD-DEM Coupled with Empirical Formulas	4

Remaining Useful Life Prediction of Nuclear Power Machinery Based on an Exponential Degradation Model	4
Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors	4
RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China	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
A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants	4
Studies on Optimal Strategy to Adopt Nuclear Power Plants into Saudi Arabian Energy System Using MESSAGE Tool	4
Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations	3
Public Health Effects of Radioactive Airborne Effluents from Nuclear and Coal-Fired Power Plant	3
Interim Storage of the Dalat Nuclear Research Reactor: Radiation Safety Analysis	3
Development and Validation of Rapid 3D Radiation Field Evaluation Technique for Nuclear Power Plants	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
Power Level Control of Nuclear Power Plant Based on Asymptotical State Observer under Neutron Sensor Fault	3
Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM	3
Xe Ion Irradiation-Induced Microstructural Evolution and Hardening Effect of Nickel-Base Superalloy	3
The Research of Fault Diagnosis of Nuclear Power Plant Based on ELM-AdaBoost.SAMME	3
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method	3
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway	3
Source Term Derivation and Radioactive Release Evaluation for JRTR Research Reactor under Severe Accident	3
COMSOL Simulation for Design of Induction Heating System in VULCAN Facility	3
Studies on Key Effect Factors of Natural Circulation Characteristics for Advanced PWR Reactor Cavity Flooding System	3
Vehicle Transport Security System Based on the Self-Security Intelligence of Radioactive Material	3
Radiation Resistance of a Structural Material Based on Modified Titanium Hydride	3
Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System	3
Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response	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
Control Rod Modeling and Worth Calculation for a Typical 1100 MWe Nuclear Power Plant Using WIMS/D4 and CITATION	3