Science and Technology of Nuclear Installations

Mechanical Properties in Nuclear Installation and the Relevant Measurement Methods

Using CFD as Preventative Maintenance Tool for the Cold Neutron Source Thermosiphon System

Sizing of the Vacuum Vessel Pressure Suppression System of a Fusion Reactor Based on a Water-Cooled Blanket, for the Purpose of the Preconceptual Design

Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator

Cost Estimation and Efficiency Analysis of Korean CANDU Spent Fuel Disposal Alternatives in Consideration of Future Price Volatility

Development of End Plug Welding Technique for SFR Fuel Rod Fabrication

Vibration Control of Nuclear Power Plant Piping System Using Stockbridge Damper under Earthquakes

PWR Containment Shielding Calculations with SCALE6.1 Using Hybrid Deterministic-Stochastic Methodology

Progress of Particle Flow, Fluid/Solid Mechanics, and Heat Transfer in Advanced Gas/Water Nuclear Reactors

Radiation Protection Practices during the Helium Circulator Maintenance of the 10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10)

Development of Vacuum Vessel Design and Analysis Module for CFETR Integration Design Platform

Radioactive Source Specification of Bushehr’s VVER-1000 Spent Fuels

Thermal Analysis for the Dense Granular Target of CIADS

The Investigation of Nonavailability of Passive Safety Systems Effects on Small Break LOCA Sequence in AP1000 Using RELAP5 MOD 4.0

Radiation Dose Calculations for a Hypothetical Accident in Xianning Nuclear Power Plant

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents: 2016

Mechanical Properties in Nuclear Installation and the Relevant Measurement Methods

Using CFD as Preventative Maintenance Tool for the Cold Neutron Source Thermosiphon System

Sizing of the Vacuum Vessel Pressure Suppression System of a Fusion Reactor Based on a Water-Cooled Blanket, for the Purpose of the Preconceptual Design

Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator

Cost Estimation and Efficiency Analysis of Korean CANDU Spent Fuel Disposal Alternatives in Consideration of Future Price Volatility

Development of End Plug Welding Technique for SFR Fuel Rod Fabrication

Vibration Control of Nuclear Power Plant Piping System Using Stockbridge Damper under Earthquakes

PWR Containment Shielding Calculations with SCALE6.1 Using Hybrid Deterministic-Stochastic Methodology

Progress of Particle Flow, Fluid/Solid Mechanics, and Heat Transfer in Advanced Gas/Water Nuclear Reactors

Radiation Protection Practices during the Helium Circulator Maintenance of the 10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10)

Development of Vacuum Vessel Design and Analysis Module for CFETR Integration Design Platform

Radioactive Source Specification of Bushehr’s VVER-1000 Spent Fuels

Thermal Analysis for the Dense Granular Target of CIADS

The Investigation of Nonavailability of Passive Safety Systems Effects on Small Break LOCA Sequence in AP1000 Using RELAP5 MOD 4.0

Radiation Dose Calculations for a Hypothetical Accident in Xianning Nuclear Power Plant