Parametric Analysis of the Compact and Long-Term-Operable Passive Residual Heat Removal System

2024-9-17

Development and Experimental Validation of a Heat Transfer Model for Spilled Molten Salt Pools

2024-9-13

Analysis of a Selected Experiment of the OSU-MASLWR Test Facility Regarding Heat Transfer in Helically Coiled Steam Generators Using AC ² -ATHLET

2024-9-13

Impact of Flexible Advanced Nuclear Reactors on Optimal Planning of Distributed Nuclear Renewable Integrated Energy Systems

2024-9-4

Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark

2024-9-4

Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample

2024-9-4

Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications

2024-8-30

Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation

2024-8-29

High-Fidelity Simulation of the Light-to-Dense Stratification Transient in the HiRJET Facility

2024-8-23

Utility and Industry Perceptions of Control Room Modernization Over the Last 10 Years

2024-8-23

Experimentally Validated Potential Theory Approach for Investigation of the Flow Field Structure of an Open Pool of a Nuclear Reactor

2024-8-19

Simulation and Mitigation of False Data Injection Cyberattacks on a Space Nuclear Reactor Power System

2024-8-13

Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor

2024-8-13

Numerical Study on Subcooled Boiling Flow and Heat Transfer Characteristics in Helical Cruciform Fuel Assembly

2024-8-13

Numerical Simulation of Steam Jet Condensation Through a Triple Nozzle Submerged into a Subcooled Water Pool

2024-8-13

Determining the Position of Gamma-Ray Interaction Using Large Scintillation Detectors and the Least Number of Photomultiplier Tubes

2024-8-12

Response to the Seawater Contamination Event at Hamaoka Unit 5 and the Effects of Corrosion by Seawater

2024-8-12

Participatory Development of Virtual Reality Training for Nuclear Power Plant Field Operators

2024-8-8

Numerical Investigation of Melting in Pressurized Water Reactor Fuel Rod Considering Operational Parameters of the Core

2024-8-8

Validation of McCARD Monte Carlo Calculation Code Against NAA Experiments Using Rare Earth Element Certified Reference Material Activated at JRTR

2024-8-7

Robust Design of Electrical System for Nuclear Plants to Prevent a Nuclear Accident During an Emergency Situation

2024-8-7

Large-scale Multiphysics Simulations of Small Modular Reactors Operating in Natural Circulation

2024-8-7

Investigation of Machine Learning Regression Techniques to Predict Critical Heat Flux Over a Large Parameter Space

2024-8-5

Explainable, Deep Reinforcement Learning–Based Decision Making for Operations and Maintenance

2024-8-2

Foreword: Selected papers from the 2022 International High-Level Radioactive Waste Management Conference

2024-8-2

Implementing Component Degradations into a Modelica Model of an iPWR System to Develop Health Monitoring Techniques

2024-8-2

Feasibility of a Small, Low-Power RTG Concept Utilizing a GPHS Heat Source

2024-7-30

Recent Developments and Findings of Heat Pipe Experiments for Microreactor Applications

2024-7-29

Hazard Identification Risk Assessment Onsite Survey for External Human-Induced Events Aspect of the Nuclear Power Plant in West Kalimantan, Indonesia

2024-7-26

A RELAP5-3D Model of the Lobo Lead Loop

2024-7-26

Computational Optimization of ^{133 <i>m</i>} Xe Production in the Washington State University TRIGA Reactor

2024-7-24

Analysis of the Long-Term Interaction Between Molten Core and Dry Concrete at Fukushima Daiichi Unit 1

2024-7-24

Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants

2024-7-23

Performance Analysis of Water Heat Pipe for Application of the Passive Cooling System in Nuclear Power Plants

2024-7-23

Design and Development of a Portable Neutron Detection System Based on a ⁶ Li-Doped ZnS(Ag) Scintillator

2024-7-23

Performance Analysis of U ₃ Si ₂ -Al Fuel with Density of 2.96 gU/cm ³ and Burnup of 56%

2024-7-23

Fiberoptic Laser-Induced Breakdown Spectroscopy System for in situ Measurement in a Hazardous Environment

2024-7-22

Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding

2024-7-22

Implementation of a Drift Flux Model into SAM with Development of a Verification and Validation Test Suite for Modeling of Noncondensable Gas Mixtures

2024-7-22

Neutronics–Thermal-Hydraulics–Coupled Transient Analysis for Reactor Power Change in an Inclined Offshore Floating Boiling Water Reactor

2024-7-22

Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications

2024-7-19

Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application

2024-7-18

Surface-Activated Graphite Oxide Nanosheets with Promoted U(VI) Adsorption Performance

2024-7-18

Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm

2024-7-18

Processes and Interactions of Potential Relevance for Deep Geological Disposal of HLW and L/ILW at the Same Site—International Approaches and Transferability to the German Site Selection

2024-7-17

Discrete Element Method Simulation of Vibratory Filling of Convoluted Hot Isostatic Pressing Canisters Using Idaho Calcine Waste Simulant

2024-7-17

CFD Modeling of Aerosol Transport and Deposition Using a Drift-Flux Model

2024-7-12

A Sociotechnical Readiness Level Framework for the Development of Advanced Nuclear Technologies

2024-7-11

An Optimal Radiation Shield Design of a Small Modular Nuclear Power Reactor by Genetic Algorithm

2024-7-10

Analyses of Jet Buoyant Flow in a Multicompartment Containment Using an Open-Source Solver

2024-7-10