Science and Technology of Nuclear Installations

Engineering Design of a Mechanical Decladder for Spent Nuclear Rod-Cuts

Multilayer Shielding Design for Intermediate Radioactive Waste Storage Drums: A Comparative Study between FLUKA and QAD-CGA

Applicability of Pseudoprobabilistic Method of Liquefaction Hazard Assessment for Nuclear Power Plants at Diffuse Seismicity Sites

Analysis of the Effect of Severe Accident Scenario on Debris Properties in Lower Plenum of Nordic BWR Using Different Versions of MELCOR Code

The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure

A Modified Multiobjective Self-Adaptive Differential Evolution Algorithm and Its Application on Optimization Design of the Nuclear Power System

Experimental and CFD Investigation on Flow Behaviors of a NPP Pump under Natural Circulation Condition

Study on Performance of Mesoscopic Impactor Filters for Aerosol Removal

A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks

Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario

Validation of Modified ART Mod 2 Code through Comparison with Aerosol Deposition of Cesium Compound in Phébus FPT3 Containment Vessel

Experimental Investigation of Decontamination Factor Dependence on Aerosol Concentration in Pool Scrubbing

Benchmarking COMSOL Multiphysics Single-Subchannel Thermal-Hydraulic Analysis of a TRIGA Reactor with RELAP5 Results and Experimental Data

Numerical Investigation of Natural Convective Condensation with Noncondensable Gases in the Reactor Containment after Severe Accidents

Analysis of Variance for Item Differences in Verification Data with Unknown Groups

Investigation of the Equivalent Test Condition for the Seismic Safety Assessment of a Spent Fuel Pool with regard to Sloshing Behavior

Study on 3D Pore Characteristics of Carbon Materials in HTGR by Micro-CT and HPMI Methods

Experimental and Numerical Investigation of Temperature Distribution on Reactor Pressure Vessel Support under Operating Conditions

The Forecasting of Corrosion Damage of Structural Materials during Dry Long-Term Storage of RD BN-350 SNF with CC-19 SFA

Simulation of the Thermal Conditions of Cask with Fuel Assemblies of BN-350 Reactor for Dry Storage

Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System

A Combined Method for Predicting the Boron Deposited Mass and the CIPS Risk

Design and Verification of Reactor Power Control Based on Stepped Dynamic Matrix Controller

An Integral Numerical Analysis of Impact of a Commercial Aircraft on Nuclear Containment

Development of PYMUS+ Code for Quantitative Evaluation of Nuclear Material Accounting (NMA) System

Conceptual Study on Recriticality Prevention Core Having Duplex Pellets with Neutron Absorber in Outer Core in a Fast Reactor

Boiling Heat Transfer and Critical Heat Flux Enhancement Using Electrophoretic Deposition of SiO2 Nanofluid

Fretting Wear and Fatigue Life Analysis of Fuel Bundles Subjected to Turbulent Axial Flow in CEFR

Blowout Accident Impact Analysis Method for the Siting of Offshore Floating Nuclear Power Plant in Offshore Oil Fields

Logistical Simulation Modeling for Planning a Soil Remediation Process

Stability of Tungsten Crucible against Uranium, Rare Earth, Cadmium, and Chlorides for Cathode Process in Pyroprocessing

Standalone Containment Analysis of Four Phébus Tests with the ASTEC and the MELCOR Codes

Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly

Chemical Forms of Important Fission Products in Primary Circuit of HTR-PM under Conditions of Normal Operation and Overpressure and Water Ingress Accidents: A Study with a Chemical Thermodynamics Approach

A Conceptual Framework for Equipment Maintenance Automation under a Pyroprocessing Automation Framework

Contribution of Ternary Reaction to Pd Sorption on MX-80 in Na-Ca-Cl Solution at High Ionic Strength

A Fracture Criterion for Prediction of Fracture Initiation of Metal Materials at Various Stress States for Nuclear Waste Storage

Three-Dimensional Measurement of TRISO Coated Particle Using Micro Computed Tomography

The Trimming-Based Design Method for PWR Coolant Flow Distribution Device

Impact of Strontium and Krypton Release from Ghana’s MNSR following a Conjectural Accident Scenario

Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings