Science and Technology of Nuclear Installations

An Efficient Scheme for Coupling OpenMC and FLUENT with Adaptive Load Balancing

Failure Fraction Calculation of the TRISO-Coated Particle Using X-Ray Computed Tomography

Detection of Illegal Movement in Radioactive Material Transportation Security Systems

Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method

The Implementation of Diverse Actuation System in ACPR1000 Nuclear Power Plants

Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident

Numerical Investigation on Turbulent Flow and Heat Transfer of Helium-Xenon Gas Mixture in a Circular Tube

Studying Disturbance Wave Velocity and Wall Shear Stress of Vertical Upward Annular Flow in Narrow Rectangular Channel

A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants

COMSOL Simulation for Design of Induction Heating System in VULCAN Facility

Prediction of the Loss of Feed Water Fault Signatures Using Machine Learning Techniques

Development and Experimental Validation for Quantifying the Moisture Carryover in a Moisture Separator Using an Air/Water Test Facility

Study on the Sensitivity and Uncertainty of Nuclear Data to the Sodium-Cooled Linear Breed-and-Burn Fast Reactor Using SCALE6.2 Code

Uranium Decontamination from Waste Soils by Chlorination with ZrCl₄ in LiCl-KCl Eutectic Salt

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

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents

An Efficient Scheme for Coupling OpenMC and FLUENT with Adaptive Load Balancing

Failure Fraction Calculation of the TRISO-Coated Particle Using X-Ray Computed Tomography

Detection of Illegal Movement in Radioactive Material Transportation Security Systems

Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method

The Implementation of Diverse Actuation System in ACPR1000 Nuclear Power Plants

Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident

Numerical Investigation on Turbulent Flow and Heat Transfer of Helium-Xenon Gas Mixture in a Circular Tube

Studying Disturbance Wave Velocity and Wall Shear Stress of Vertical Upward Annular Flow in Narrow Rectangular Channel

A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants

COMSOL Simulation for Design of Induction Heating System in VULCAN Facility

Prediction of the Loss of Feed Water Fault Signatures Using Machine Learning Techniques

Development and Experimental Validation for Quantifying the Moisture Carryover in a Moisture Separator Using an Air/Water Test Facility

Study on the Sensitivity and Uncertainty of Nuclear Data to the Sodium-Cooled Linear Breed-and-Burn Fast Reactor Using SCALE6.2 Code

Uranium Decontamination from Waste Soils by Chlorination with ZrCl₄ in LiCl-KCl Eutectic Salt

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

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents

An Efficient Scheme for Coupling OpenMC and FLUENT with Adaptive Load Balancing

Failure Fraction Calculation of the TRISO-Coated Particle Using X-Ray Computed Tomography

Detection of Illegal Movement in Radioactive Material Transportation Security Systems

Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method

The Implementation of Diverse Actuation System in ACPR1000 Nuclear Power Plants

Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident

Numerical Investigation on Turbulent Flow and Heat Transfer of Helium-Xenon Gas Mixture in a Circular Tube

Studying Disturbance Wave Velocity and Wall Shear Stress of Vertical Upward Annular Flow in Narrow Rectangular Channel

A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants

COMSOL Simulation for Design of Induction Heating System in VULCAN Facility

Prediction of the Loss of Feed Water Fault Signatures Using Machine Learning Techniques

Development and Experimental Validation for Quantifying the Moisture Carryover in a Moisture Separator Using an Air/Water Test Facility

Study on the Sensitivity and Uncertainty of Nuclear Data to the Sodium-Cooled Linear Breed-and-Burn Fast Reactor Using SCALE6.2 Code

Uranium Decontamination from Waste Soils by Chlorination with ZrCl4 in LiCl-KCl Eutectic Salt

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

Uranium Decontamination from Waste Soils by Chlorination with ZrCl₄ in LiCl-KCl Eutectic Salt