Science and Technology of Nuclear Installations

Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors

Solution of the Static Deflection Mode Shape Function of the Cantilever Beam under Transverse Flow Based on the Boundary Shooting Method

Study on the Applicability of Neutron Radiation Damage Method Used for High-Temperature Superconducting Tape Based on Geant4 and SRIM

Xe Ion Irradiation-Induced Microstructural Evolution and Hardening Effect of Nickel-Base Superalloy

Technical Options and Cost Estimates for Spent Nuclear Fuel Management at the Barakah Nuclear Power Plants

Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models

Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl₃ Molten Salt

Electrochemical Deposition of U and RE Elements Using the Stirred Liquid Cadmium Cathode in LiCl-KCl Molten Salts

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

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents: 2021

Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors

Solution of the Static Deflection Mode Shape Function of the Cantilever Beam under Transverse Flow Based on the Boundary Shooting Method

Study on the Applicability of Neutron Radiation Damage Method Used for High-Temperature Superconducting Tape Based on Geant4 and SRIM

Xe Ion Irradiation-Induced Microstructural Evolution and Hardening Effect of Nickel-Base Superalloy

Technical Options and Cost Estimates for Spent Nuclear Fuel Management at the Barakah Nuclear Power Plants

Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models

Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl₃ Molten Salt

Electrochemical Deposition of U and RE Elements Using the Stirred Liquid Cadmium Cathode in LiCl-KCl Molten Salts

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

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents: 2021

Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors

Solution of the Static Deflection Mode Shape Function of the Cantilever Beam under Transverse Flow Based on the Boundary Shooting Method

Study on the Applicability of Neutron Radiation Damage Method Used for High-Temperature Superconducting Tape Based on Geant4 and SRIM

Xe Ion Irradiation-Induced Microstructural Evolution and Hardening Effect of Nickel-Base Superalloy

Technical Options and Cost Estimates for Spent Nuclear Fuel Management at the Barakah Nuclear Power Plants

Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models

Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt

Electrochemical Deposition of U and RE Elements Using the Stirred Liquid Cadmium Cathode in LiCl-KCl Molten Salts

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

Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl₃ Molten Salt