Science and Technology of Nuclear Installations

RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China

The Research of Fault Diagnosis of Nuclear Power Plant Based on ELM-AdaBoost.SAMME

Online Simulation of Nuclear Power Plant Primary Systems

Metallic Fuel Fabrication Process Development in Remote Fuel Fabrication Mock-Up at KAERI

Interim Storage of the Dalat Nuclear Research Reactor: Radiation Safety Analysis

An Economic Cost Assessment on HALEU Fuels for Small Modular Reactors

Reliability Assessment for a Safety-Related Digital Reactor Protection System Using Event-Tree/Fault-Tree (ET/FT) Method

Manufacturing and Testing of an In Situ Stretching Sample Environment Equipment for Neutron Scattering Experiments

Core Design of a Small Pressurized Water Reactor with AP1000 Fuel Assembly Using SRAC and COBRA-EN Codes

Numerical Study of the Air Ingress Accident of the HTR-PM and Possible Mitigation Measures

Assessment of Lifetime Attributable Risk for Public Health Sustainability from the Fukushima Accident

A New Precursor Integral Method for Solving Space-Dependent Kinetic Equations in Neutronic and Thermal-Hydraulic Coupling System

Analyzing Design Considerations for Disassembly of Spent Nuclear Fuel during Head-End Process of Pyroprocessing

Bubble Bursting and Drainage Characteristics at the Free Surface of a Liquid Pool with an Aerosol

Electrochemical Behavior of CsI in LiCl Molten Salt

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents: 2020

RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China

The Research of Fault Diagnosis of Nuclear Power Plant Based on ELM-AdaBoost.SAMME

Online Simulation of Nuclear Power Plant Primary Systems

Metallic Fuel Fabrication Process Development in Remote Fuel Fabrication Mock-Up at KAERI

Interim Storage of the Dalat Nuclear Research Reactor: Radiation Safety Analysis

An Economic Cost Assessment on HALEU Fuels for Small Modular Reactors

Reliability Assessment for a Safety-Related Digital Reactor Protection System Using Event-Tree/Fault-Tree (ET/FT) Method

Manufacturing and Testing of an In Situ Stretching Sample Environment Equipment for Neutron Scattering Experiments

Core Design of a Small Pressurized Water Reactor with AP1000 Fuel Assembly Using SRAC and COBRA-EN Codes

Numerical Study of the Air Ingress Accident of the HTR-PM and Possible Mitigation Measures

Assessment of Lifetime Attributable Risk for Public Health Sustainability from the Fukushima Accident

A New Precursor Integral Method for Solving Space-Dependent Kinetic Equations in Neutronic and Thermal-Hydraulic Coupling System

Analyzing Design Considerations for Disassembly of Spent Nuclear Fuel during Head-End Process of Pyroprocessing

Bubble Bursting and Drainage Characteristics at the Free Surface of a Liquid Pool with an Aerosol

Electrochemical Behavior of CsI in LiCl Molten Salt