| Effect of Subcooling on Pool Boiling of Water from Sintered Copper Microporous Coating at Different Orientations |
4 |
| Applicability of Pseudoprobabilistic Method of Liquefaction Hazard Assessment for Nuclear Power Plants at Diffuse Seismicity Sites |
3 |
| Study on Performance of Mesoscopic Impactor Filters for Aerosol Removal |
2 |
| Benefits of Seismic Isolation for Nuclear Structures Subjected to Severe Earthquake |
2 |
| Engineering Design of a Mechanical Decladder for Spent Nuclear Rod-Cuts |
2 |
| A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks |
2 |
| Effects of Diameters on Countercurrent Flow Limitation at a Square Top End in Vertical Pipes |
2 |
| Analysis of the Effect of Severe Accident Scenario on Debris Properties in Lower Plenum of Nordic BWR Using Different Versions of MELCOR Code |
2 |
| Numerical Study of Bubble Rising and Coalescence Characteristics under Flow Pulsation Based on Particle Method |
2 |
| Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO2 Brayton Cycle as Power Conversion System |
1 |
| Experimental and Numerical Studies on Sloshing Dynamics of PCS Water Tank of Nuclear Island Building |
1 |
| RELAP5/MOD3.3 Analysis of the Loss of External Power Event with Safety Injection Actuation |
1 |
| 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 |
1 |
| Process of Air Ingress during a Depressurization Accident of GTHTR300 |
1 |
| Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors |
1 |
| Multilayer Shielding Design for Intermediate Radioactive Waste Storage Drums: A Comparative Study between FLUKA and QAD-CGA |
1 |
| Temperature Profile Measurement in Simulated Fuel Assembly Structure with Wire-Mesh Technology |
1 |
| Moisture Transfer Model and Simulation for Dehumidification of HTGR Core |
1 |
| Design of the Online Gross gamma Monitoring Instrument at the Exit of the Helium Purification System in HTR-PM |
1 |
| Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor |
1 |
| A New Accurate Numerical Method Based on Shifted Chebyshev Series for Nuclear Reactor Dynamical Systems |
1 |
| Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly |
1 |
| Assessment of the Radioactive Contamination of the RBMK-1500 Reactor's Steam Pipelines and High Pressure Rings |
1 |
| Innovative Design of Replacement Device for Vulnerable Parts in the Nuclear Radiation Environment |
1 |
| Development of PYMUS plus Code for Quantitative Evaluation of Nuclear Material Accounting (NMA) System |
1 |
| Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor |
1 |
| A Novel Nonlinear BWR Stability Indicator Based on the Sample Entropy |
1 |
| Numerical Investigation of Natural Convective Condensation with Noncondensable Gases in the Reactor Containment after Severe Accidents |
1 |
| Effect of Fe2O3 on the Immobilization of High-Level Waste with Magnesium Potassium Phosphate Ceramic |
1 |
| Condition Monitoring of Sensors in a NPP Using Optimized PCA |
1 |
| Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress |
1 |
| Local Void Fractions and Bubble Velocity in Vertical Air-Water Two-Phase Flows Measured by Needle-Contact Capacitance Probe |
1 |
| 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 |
0 |
| A Modified Multiobjective Self-Adaptive Differential Evolution Algorithm and Its Application on Optimization Design of the Nuclear Power System |
0 |
| Impact of Strontium and Krypton Release from Ghana's MNSR following a Conjectural Accident Scenario |
0 |
| Investigation of the Equivalent Test Condition for the Seismic Safety Assessment of a Spent Fuel Pool with regard to Sloshing Behavior |
0 |
| Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario |
0 |
| Analysis of Loss of Essential Power System Reported in Nuclear Power Plants |
0 |
| Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics |
0 |
| Evaluation of Gas Migration and Rock Damage Characteristics for Underground Nuclear Waste Storage Based on a Coupled Model |
0 |
| Simulation of the Thermal Conditions of Cask with Fuel Assemblies of BN-350 Reactor for Dry Storage |
0 |
| Bulk Handling Facility Modeling and Simulation for Safeguards Analysis |
0 |
| 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 |
0 |
| The Forecasting of Corrosion Damage of Structural Materials during Dry Long-Term Storage of RD BN-350 SNF with CC-19 SFA |
0 |
| Standalone Containment Analysis of Four Phebus Tests with the ASTEC and the MELCOR Codes |
0 |
| A Design of Parameters with Supercritical Carbon Dioxide Brayton Cycle for CiADS |
0 |
| Evaluation of Antimony Tri-Iodide Crystals for Radiation Detectors |
0 |
| Analysis of Variance for Item Differences in Verification Data with Unknown Groups |
0 |
| Validation of Modified ART Mod 2 Code through Comparison with Aerosol Deposition of Cesium Compound in Phebus FPT3 Containment Vessel |
0 |
| Fretting Wear and Fatigue Life Analysis of Fuel Bundles Subjected to Turbulent Axial Flow in CEFR |
0 |
