Science and Technology of Nuclear Installations: Vol 2018, No 1

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Science and Technology of Nuclear Installations

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CFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor

Evaluation of Antimony Tri-Iodide Crystals for Radiation Detectors

The R&D of HTR-STAC Program Package: Source Term Analysis Codes for Pebble-Bed High-Temperature Gas-Cooled Reactor

Effects of Diameters on Countercurrent Flow Limitation at a Square Top End in Vertical Pipes

Validation of the COTENP Code: A Steady-State Thermal-Hydraulic Analysis Code for Nuclear Reactors with Plate Type Fuel Assemblies

ASTEC–MAAP Comparison of a 2 Inch Cold Leg LOCA until RPV Failure

Innovative Design of Replacement Device for Vulnerable Parts in the Nuclear Radiation Environment

Temperature Profile Measurement in Simulated Fuel Assembly Structure with Wire-Mesh Technology

Design of the Online Gross γ Monitoring Instrument at the Exit of the Helium Purification System in HTR-PM

Multiphysical Simulations for the IAEA/ISCP Benchmark Model on the Contact of Pressure Tube and Calandria Tube in the Moderator System of CANDU-6 PHWR

A Novel Nonlinear BWR Stability Indicator Based on the Sample Entropy

Large Scale Experiments Representing a Containment Natural Circulation Loop during an Accident Scenario

Research of PWR Pressurizer Insurge Characteristics on Three-Dimensional Transient Modeling

Bulk Handling Facility Modeling and Simulation for Safeguards Analysis

In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor

Uniformity Assessment of TRISO Fuel Particle Distribution in Spherical HTGR Fuel Element Using Voronoi Tessellation and Delaunay Triangulation

A New Accurate Numerical Method Based on Shifted Chebyshev Series for Nuclear Reactor Dynamical Systems

Benefits of Seismic Isolation for Nuclear Structures Subjected to Severe Earthquake

Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO2 Brayton Cycle as Power Conversion System

Process of Air Ingress during a Depressurization Accident of GTHTR300

Properties of a Prototype Corium of Nuclear Reactor

Assessment of Adequate Margin to Liquefaction for Nuclear Power Plants

Preliminary Selection of Device Materials to Locally Transform Thermal into SFR Neutron Spectrum

ROSA/LSTF Tests and Posttest Analyses by RELAP5 Code for Accident Management Measures during PWR Station Blackout Transient with Loss of Primary Coolant and Gas Inflow

Effect of Subcooling on Pool Boiling of Water from Sintered Copper Microporous Coating at Different Orientations

A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident

Moisture Transfer Model and Simulation for Dehumidification of HTGR Core

Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor

Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress

Theoretical Solutions for Dynamic Characteristics of Liquid Annular Seals with Herringbone Grooves on the Stator Based on Bulk-Flow Theory

Analysis of Spatial Discretization Error Estimators Implemented in ARES Transport Code for SN Equations

Analysis of Loss of Essential Power System Reported in Nuclear Power Plants

Analysis of Steam Explosion under Conditions of Partially Flooded Cavity and Submerged Reactor Vessel

Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor

Evaluation of Gas Migration and Rock Damage Characteristics for Underground Nuclear Waste Storage Based on a Coupled Model

A Design of Parameters with Supercritical Carbon Dioxide Brayton Cycle for CiADS

Numerical Simulation of a No-Insulation BSCCO Toroidal Magnet Applied in Magnetic Confinement Fusion

Experimental and Numerical Studies on Sloshing Dynamics of PCS Water Tank of Nuclear Island Building

Determination of an Effective Detector Position for Pulsed-Neutron-Source Alpha Measurement by Time-Dependent Monte Carlo Neutron Transport Simulations

RELAP5/MOD3.3 Analysis of the Loss of External Power Event with Safety Injection Actuation

Numerical Simulation of Decontamination of Airborne Fission Products during In-Vessel Release Phase by Containment Spray

Local Void Fractions and Bubble Velocity in Vertical Air-Water Two-Phase Flows Measured by Needle-Contact Capacitance Probe

Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors

Pressure Waves due to Rapid Evaporation of Water Droplet in Liquid Lead Coolant

The Feasibility Study for Multigeometries Identification of Uranium Components Using PCA-LSSVM Based on Correlation Measurements

Study on the Comprehensive Properties and Microstructures of A3-3 Matrix Graphite Related to the High Temperature Purification Treatment

Simulation of Turbulent Wake at Mixing of Two Confined Horizontal Flows

Design Optimization of HANARO Irradiation Capsule for Long-Term Irradiation Testing

Calibration of the Absolute Efficiency of Well-Type NaI(Tl) Scintillation Detector in 0.121–1.408 MeV Energy Range

Strategy Evaluation for Cavity Flooding during an ESBO Initiated Severe Accident

Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon

Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics

On the One-Dimensional Modeling of Vertical Upward Bubbly Flow

Condition Monitoring of Sensors in a NPP Using Optimized PCA

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Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO₂ Brayton Cycle as Power Conversion System

Analysis of Spatial Discretization Error Estimators Implemented in ARES Transport Code for S_N Equations