Science and Technology of Nuclear Installations

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 2021-04-01 to 2025-04-01.)
ArticleCitations
A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants33
Assessment of Cesium Compound Behavior during Simultaneous Failure of Reactor Pressure Vessels and Spent Fuel Pools Using Modified ART Mod 2: Fukushima Daiichi Accident Simulation19
Detecting Unauthorized Movement of Radioactive Material Packages in Transport with an Adam-Optimized BP Neural Network Model13
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 110
Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions9
Optimization of the n/γ Pulse Shape Discrimination Performance of Plastic Scintillator Coupled With SiPM Arrays8
Count Loss Evaluation for Accuracy Enhancement of a FPGA‐Based Gamma Spectroscopy6
Nuclear Power Sustainability Path for China from the Perspective of Operations6
Deep Learning–Based Fault Identification Testing Experiment for Bellows Valves6
Prediction of the Loss of Feed Water Fault Signatures Using Machine Learning Techniques5
Effect of Chloride Ions on Electrochemical Behavior of Canister Materials5
Migration Simulation of Radioactive Soil Particles in the Atmospheric Environment Using CFD-DEM Coupled with Empirical Formulas5
Numerical Investigation on Turbulent Flow and Heat Transfer of Helium-Xenon Gas Mixture in a Circular Tube5
Study on Probabilistic Safety Goals for Multimodule High-Temperature Gas-Cooled Reactor Based on Chinese Societal Risks5
A Hybrid Method to Predict the Remaining Useful Life of Scroll Wheel of Control Rod Drive Mechanism5
Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material4
Bayesian Uncertainty Quantification of Reflooding Model With PSO–Kriging and PCA Approach4
Application of EDG AOT Extension Based on the Risk-Informed Method in NPPs4
Evaluation of Worker Radiation Exposure during the Kori Unit 1 Steam Generator Dismantling Process4
Prediction of Crack Propagation Directions in Dissimilar Metal‐Welded Joints Using Phase‐Field Models and Discussion of Its Mechanisms4
A Reduced Order Model Based on ANN-POD Algorithm for Steady-State Neutronics and Thermal-Hydraulics Coupling Problem4
Acceptable Level of Acceptance and the Affecting Factors: What Is the Acceptable Public Acceptance of Building a Nuclear Power Plant4
Investigation of Oxidation and Counter-Oxidation in a One-Quarter Circular Geometry due to Shadow Corrosion4
A New Experimental Method for the Nonlinear Modal Parameter Identification of a Pressurized Water Reactor Fuel Assembly4
Study of the Design and Assembly of a High Harmonic Fast Wave Antenna for an LAPD3
A Study on Radiological Evaluation According to Exposure Conditions in Mobile Radiochemistry Analysis Facilities Using Worker’s Dose Evaluation Code3
Calculation and Analysis of the Source Term of the Reactor Core Based on Multivariate Analysis of Variance3
Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models3
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger3
Source Reconstruction of Atmospheric Releases by Bayesian Inference and the Backward Atmospheric Dispersion Model: An Application to ETEX-I Data3
Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method3
Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt3
Uranium Recovery from Phosphates for Self-Sufficient Nuclear Power in the Eastern Mediterranean3
Control Rod Modeling and Worth Calculation for a Typical 1100 MWe Nuclear Power Plant Using WIMS/D4 and CITATION3
Development and Experimental Validation for Quantifying the Moisture Carryover in a Moisture Separator Using an Air/Water Test Facility3
Mechanical Properties Evaluation and Crack Propagation Behavior in Dissimilar Metal Welded Joints of 304 L Austenitic Stainless Steel and SA508 Low-Alloy Steel3
The Study of Dosimetric Characteristics of the XHA600D Medical Linear Accelerator Based on a Monte Carlo Code2
Research on Radionuclide Diffusion Mechanism in the Ocean and Emergency Response under Oceanic Radioactive Events2
Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump2
Research and Implementation of SVDU Simulator Based on Emulation Technology2
A Data-Driven Fault Prediction Method for Nuclear Power Systems Based on End-to-End Deep Learning Framework2
Integrated Security System (ISS) Design and Evaluation for Commercial Nuclear Power Plant2
Simulation of Ionizing/Displacement Synergistic Effects on NPN Bipolar Transistors Irradiated by Mixed Neutrons and Gamma Rays2
Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA2
Analysis of Heat Release Processes inside Storage Facilities Containing Irradiated Nuclear Graphite2
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall2
COMSOL Simulation for Design of Induction Heating System in VULCAN Facility2
Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident2
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants2
Advancing Small Modular Reactor Technology Assessment in the Czech Republic, Egypt, and Poland2
Effect of Inhomogeneous Mechanical Properties on the Stress-Strain Field at the Crack Tip and Crack Growth Direction in Dissimilar Metal Welded Joints2
Cracking Driving Force at the Tip of SCC under Heterogeneous Material Mechanics Model of Safe-End Dissimilar Metal-Welded Joints in PWR2
Studying Disturbance Wave Velocity and Wall Shear Stress of Vertical Upward Annular Flow in Narrow Rectangular Channel2
Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART2
Methods for Predicting the Minimum Temperature of the Outage Loop and the Maximum Power Caused by the Low-Temperature Coolant2
Study on the Dispersion of Radionuclides under Different Hydrological Conditions of Spent Fuel Shipping in Daya Bay2
Radiation Tolerant 3D Laser Scanner for Structural Inspections in Nuclear Reactor Vessels and Fuel Storage Pools2
0.30028605461121