Science and Technology of Nuclear Installations

Design of Control System of Once-Through Steam Generator Based on Proximal Policy Optimization Algorithm

Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump

Determination of the Activity Inventory in the Structural Components of the Dalat Nuclear Research Reactor for Its Decommissioning Planning

Preliminary Study on Risk Identification and Assessment Framework for Fusion Radioactive Waste Management

The Concept of the Heat Removal System of a High-Flux Research Reactor

Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM

Oceanic Radionuclide Dispersion Method Investigation for Nonfixed Source from Marine Reactor Accident

Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response

Investigation of the Flow and Heat Transfer Characteristics and Erosion Law of Particulate in LBE on the Subchannel

Multiple Assessments on the Gamma-Ray Protection Properties of Niobium-Doped Borotellurite Glasses: A Wide Range Investigation Using Monte Carlo Simulations

Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions

Verification of the Efficacy of Passive Autocatalytic Recombiners in a Typical Pressurized Water Reactor under a Station Blackout Condition

Research on Channel Modeling and Communication Coverage of Wireless Sensor Networks in Barrier Area of Nuclear Power Plants

Interaction of Mechanical Heterogeneity and Residual Stress on Mechanical Field at Crack Tips in DMWJs

Rapid Determination of Gross Alpha/Beta Activity in Water Based on Reverse Osmosis Membrane Enrichment Pretreatment

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents: 2022

Design of Control System of Once-Through Steam Generator Based on Proximal Policy Optimization Algorithm

Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump

Determination of the Activity Inventory in the Structural Components of the Dalat Nuclear Research Reactor for Its Decommissioning Planning

Preliminary Study on Risk Identification and Assessment Framework for Fusion Radioactive Waste Management

The Concept of the Heat Removal System of a High-Flux Research Reactor

Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM

Oceanic Radionuclide Dispersion Method Investigation for Nonfixed Source from Marine Reactor Accident

Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response

Investigation of the Flow and Heat Transfer Characteristics and Erosion Law of Particulate in LBE on the Subchannel

Multiple Assessments on the Gamma-Ray Protection Properties of Niobium-Doped Borotellurite Glasses: A Wide Range Investigation Using Monte Carlo Simulations

Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions

Verification of the Efficacy of Passive Autocatalytic Recombiners in a Typical Pressurized Water Reactor under a Station Blackout Condition

Research on Channel Modeling and Communication Coverage of Wireless Sensor Networks in Barrier Area of Nuclear Power Plants

Interaction of Mechanical Heterogeneity and Residual Stress on Mechanical Field at Crack Tips in DMWJs

Rapid Determination of Gross Alpha/Beta Activity in Water Based on Reverse Osmosis Membrane Enrichment Pretreatment