Science and Technology of Nuclear Installations

A Hybrid Method to Predict the Remaining Useful Life of Scroll Wheel of Control Rod Drive Mechanism

Numerical Study of Natural Circulation Flow in Reactor Coolant System during a Severe Accident

Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations

Investigation of Oxidation and Counter-Oxidation in a One-Quarter Circular Geometry due to Shadow Corrosion

Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation

Effect of Chloride Ions on Electrochemical Behavior of Canister Materials

Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel

An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes

Remaining Useful Life Prediction of Nuclear Power Machinery Based on an Exponential Degradation Model

Study on the Dispersion of Radionuclides under Different Hydrological Conditions of Spent Fuel Shipping in Daya Bay

Uranium Recovery from Phosphates for Self-Sufficient Nuclear Power in the Eastern Mediterranean

Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway

An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants

Investigation of Loss of Feedwater (LOFW) Accident in the APR-1400 Using Fault Tree Analysis

Influence of Weak Compressibility on the Hydrodynamic Performance Evaluation of Pump Turbines in the Pump Mode

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents: 2022

A Hybrid Method to Predict the Remaining Useful Life of Scroll Wheel of Control Rod Drive Mechanism

Numerical Study of Natural Circulation Flow in Reactor Coolant System during a Severe Accident

Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations

Investigation of Oxidation and Counter-Oxidation in a One-Quarter Circular Geometry due to Shadow Corrosion

Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation

Effect of Chloride Ions on Electrochemical Behavior of Canister Materials

Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel

An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes

Remaining Useful Life Prediction of Nuclear Power Machinery Based on an Exponential Degradation Model

Study on the Dispersion of Radionuclides under Different Hydrological Conditions of Spent Fuel Shipping in Daya Bay

Uranium Recovery from Phosphates for Self-Sufficient Nuclear Power in the Eastern Mediterranean

Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway

An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants

Investigation of Loss of Feedwater (LOFW) Accident in the APR-1400 Using Fault Tree Analysis

Influence of Weak Compressibility on the Hydrodynamic Performance Evaluation of Pump Turbines in the Pump Mode