OOIR: Observatory of International Research

Papers

(The TQCC of Nuclear Technology is 2. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2022-06-01 to 2026-06-01.)

Article	Citations
Thermal-Hydraulic Core Design of a Thorium-Based Molten Salt Fast Energy Amplifier	77
Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications	41
STORAGE: A Source Term Model for Intermediate-Level Radioactive Waste	30
Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments	29
An Anisotropic Neutron Collimating System for Proton Accelerator–Generated Secondary Particles	28
Safety Classification of Modular HTGRs Based on the IAEA SSG-30 Method	28
Spatiotemporal Evaluation of Bubble Characteristics in Sodium Using Real-Time X-Ray Imaging	27
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay	19
Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles	16
Mapping the Hydrogen Economy in Ghana: The Strategic Contribution of Small Modular Reactors	15
The Design and Development of the Process Radiation Monitoring System of the High Temperature Gas-Cooled Reactor (HTGR) in China	14
Simulation of a Slow Loss-of-Flow Accident in an Open-Pool Research Reactor Using Computational Fluid Dynamics	14
FAST Irradiations, Postirradiation Examinations, and Modeling of U-Mo for Light Water Reactor Applications	14
MARVEL Authorization Process	13
Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark	13
Interpreting Thermally and Hydrodynamically Controlled Regions in Subcooled Flow Boiling	12
Optimizing Transmission Expansion for Sustainable Energy Integration in Ghana: A Multiscenario Analysis of Nuclear and Renewable Synergies Within the West African Power Pool Framework	12
Long-Lived Fission Products Transmutation in Fission-Free Thermal Accelerator-Driven Transmuter	12
Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor	12
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor	11
Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction	11
Recent ²³⁸ Pu Production Activities at Idaho National Laboratory	11
Study on Aerosol Deposition Characteristics of an Obstacle Structure During Ventilation for Fukushima Daiichi Decommissioning	11
Uncertainty Assessment of an iSMR Passive Safety System: Model Lifecycle Management Study Case	10
Liquid Film Thickness for Gas-Liquid Annular Flow Across Grid Spacer with Vanes in Simple 3 × 3 Rod Bundle Channel	10

Assessment of RELAP5-3D Code with Molten Salt Heat Transfer Experiments	10
Comprehensive Study on p-n Junction and Schottky Barrier Betavoltaic Battery with ¹⁴ C Beta-Emitting Source	10
Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors	9
Revisiting Mobile Paste Reactor Fuel	9
Boiling and Drying Accident of High-Level Liquid Waste in a Reprocessing Plant: Measurement of the Liquid-Phase Mass Transfer Coefficients of NO ₂ an	8
Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle	8
Network Graph Laplacian-Based Sensor Projection in System-Level Modeling of Liquid-Metal Loop	8
Methods for Extending the Reactor Core Lifetime of the Canadian Thermal Battery ^TM	8
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling	8
Comparison of Two Methods for Obtaining the Variabilities in a FRAM Model of a Combined Nuclear Facility Project	8
Comprehensive Study on Gamma-Ray, Neutron, and Charged Particle Shielding Properties of Glass Materials Using Analytical Methods and Monte Carlo Simulations	8
“Arturo” Nuclear Power Plant and the Technopolitics of Italian Nuclear Decommissioning	7
Data-Informed Evaluation Framework for Integrated Energy Systems: Insights from Power, Process Heat, and Hydrogen Production Applications	7
FNERCs Software for Fast Neutron Shielding Assessment Based on ENDF/B-VIII.0, ENDF/B-VIII.1, and TENDL Libraries	7
Detection of Isotopes in Urban Source Search Low-Count Gamma Spectra Using Hopfield Neural Networks	7
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys	7
The Origins of Nuclear Expertise: The Formation of Nuclear Engineering Education in the US and Sweden (1950–1979)	7
Implementation and Demonstration of the Digital Twin Certification System Remote Operations Framework	7
Adsorption Properties of Cs(I) and Co(II) on GMZ Bentonite Colloids	7
Development of a Signal Processing Software for Scintillation Detectors and Implementation on an FPGA for Fast Sensing	7
A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components	6
Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample	6
Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm	6
Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor	6
Foreword: Special Issue Featuring Papers from the 2024 Advanced Reactor Safety Topical Meeting (ARS 2024)	6
Iodine Source Term Uncertainty and Sensitivity Analysis with the Severe Accident Code ASTEC: Focus on Iodine Chemistry, Aerosol Behavior, and Containment Pressurization	6
Density Equation for Mixed Organic Solutions Containing tri- n -butyl Nitrate, n -Dodecane, Nitric Acid, and Nitrates of Heavy Metals	6
Thermal-Hydraulic Analysis of Inward and Outward Fuel Plate Buckling in a Typical MTR Reactor	6
Sociotechnical Readiness Level and Natural Language Processing: Tools for Measuring and Managing Societal Acceptance of Nuclear Energy	6
Study of the User Effect Impact in Forward Uncertainty Propagation Approaches Applied to Severe Accident	6
Validation Matrix for Pool Scrubbing Models	6
Adaptive Model Predictive Control for Heat Pipe–Cooled Microreactors Under Normal and Heat Pipe Failure Conditions	6
Development of Emergency Information System to Support Nuclear Power Plant Management in Severe Accident	6
Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks	6
MATLAB-Based Modeling and Analysis of Nuclear Power Plant Integration into Ghana’s Electrical Grid: A Dynamic Systems Approach	6
Organic Telluride Formation from Paint Solvents Under Gamma Irradiation	6
The Versatile Loop Facility: A New Infrastructure for Testing Components and Systems of Lead Fast Reactor Technology	6
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors	6
Explaining System-Level Prognostics with Established Machine Learning Methods	6
Salt Spills Analysis Methodology for KP-FHR: Two-Phase Mechanical Aerosolization and Evaporation Mass Transfer	6
CHF Enhancement by γ-Fe ₂ O ₃ Nanofluids with Pool Boiling Condition on a Downward-Facing Plane	6
An Uncertainty Quantification Method for Neutronics Parameters in the Pressurized Water Reactor Core Control System	5
Systematic Component Investigation of the Steady-State High-Temperature In-Pile Nuclear Thermal Propulsion Experimental Test Bed	5
Build-to-Replace Strategy to Reduce Operations and Maintenance Costs for Advanced Reactors	5
A Multiwire Proportional Chamber for Standardization of Large-Area Sources: Methodology and Challenges for In-House Construction	5
Is It Time for the United States to Reconsider Transmutation for Spent Nuclear Fuel?	5
Effect of Nozzle Diameter on Quenching Behavior of Simulant Material CaO-Fe₂O₃ Under Bottom Flooding Conditions	5
Sustaining Nuclear Research Infrastructure in Developing Countries: A Comprehensive Plant Life Extension Strategy for Ghana Research Reactor-1 (GHARR-1), Integrating Technical Assessments, Modernizati	5
Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application	5
Safety Benefits Assessment for Accident Tolerant Fuels in Consideration of Steam Generator Tube Degradation Using Dynamic Event Tree Analysis	5

Validation of Axpo’s SIMULATE-3K Model Against Stability Measurements of Leibstadt Nuclear Power Plant	5
Gamma-Ray Spectrometric Investigation of Rare-Earth-Doped Glasses Irradiated by Fast and Thermal Neutrons	5
Development of Two-Step Method for Fast Chloride MSR Neutronics	5
Validation of a Hybrid Domain Overlapping Coupling Between SAM and CFD Against the TALL-3D Transients	5
Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models	5
Sparse-View Neutron Computed Tomography 3-D Reconstruction via the Fast Gradient Projection Algorithm	5
Assessing the Structure-Based Turbulence Model Performance for Thermal Striping Applications Using Symmetric Jet Experiments	5
Multiphase Turbulence Modeling Using Sparse Regression and Gene Expression Programming	5
Heat Transfer Analysis of Core Melt Contact with a CANDU Calandria	5
Design and Characterization of Y ₂ O ₃ /Pr ₂ O	5
Training Autonomous Robotic Tasks Through the Use of Machine Learning in Simulated Realities	5
Radionuclide Transport in Channel Networks with Radial Diffusion in the Porous Rock Matrix	5
Assessment of Natural Radionuclide and Radiation Hazard Indices Using Data Analysis and Multivariate Statistical Approach in Duzkoy, Trabzon, Turkey	5
Two Phase Flows in Narrow Rectangular Channels	5
A RELAP5-3D Model of the Lobo Lead Loop	5
Surveillance Interval Determination for RSG-GAS Components Using Maintenance Priority Index and Weibull–Monte Carlo Simulation: Monitoring of the KLD-BRV10 Generator Set	5
Validation of a Countercurrent Gas Flow Model for Use in the Kairos Power System Analysis Module (KP-SAM) Code	5
Development and Verification of Neutron Kinetics Parameter Calculation Program Applicable to Subcritical Systems of Long-Life Reactors	5
Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL	5
Improving Accuracy of a Machine Learning Approach for Forecasting Severe Accidents	5
The Use of High-Density UN Fuel in Heat-Pipe Microreactors	5
Direct Numerical Simulation and Large Eddy Simulation of a 67-Pebble-Bed Experiment	5
Prognostics and Health Management for Maintenance-Dependent Processes	5
Equivalence of the Peierls and Serber Wartime Expressions for the Critical Radius of a Fissile Isotope	4
A Way of Analyzing an Oxide Layer on Irradiated Plate-Type Atomized U-Mo Fuel Using an EPMA and X-Ray Image Mapping	4
An Integrated Tool Set for Spent Nuclear Fuel Pool Sabotage Assessment: Coupling DEPO-Based Physical Protection Effectiveness with WSPEEDI Consequence Modeling	4
Indirect Parameterized Risk Assessment Applied to Brazilian Nuclear Sector	4
Path Toward a Breeding, Proliferation-Resistant, Thermal-Spectrum Molten Salt Reactor	4
2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE	4
Remark About “Finely Divided Metal as Nuclear Reactor Fuel”	4
Study of Turbulence and Pressure Recovery in the Heat Pipe Vapor Flow Using the Spectral-Element Method	4
Foreword: Special issue on the Nuclear Energy Advanced Modeling and Simulation Thermal Hydraulics Integrated Research Project	4
On the Development of a Novel Acoustic Flowmeter for High-Temperature Gas-Cooled Reactors	4
Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister Filling Process: Part 2	4
Comparison of Neutron Radiation Response of Conventionally Wrought Versus Additive Manufacturing Production Methods in Alloy 625	4
Numerical Simulation on Dispersion of Hydrogen Leaked in Particle Layers of Glass Beads and Soil	4
Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages	4
Neutron Energy Spectrum Measurement and Unfolding Method Based on a Single Long Lithium- or Boron-Doped Scintillator	4
The Experimental and Simulation Results of LIVE-J2 Test—Investigation on Heat Transfer in a Solid–Liquid Mixture Pool	4
Large Eddy Simulation of Low-Reynolds-Number Turbulent Flow of Low-Prandtl-Number Fluid in a Tight Lattice Bundle for Assessment of Reynolds-Averaged Navier-Stokes Turbulence Model	4
Development of RELAP5-3D Model for an Integrated Test Facility for Advanced Reactor Systems	4
Time-Dependent Experiment on Reactor Power Distribution Estimation by Ex-Core Detectors at UTR-KINKI	4
Impact of the Uncertainties Associated with Core Degradation in H ₂ Production during the In-Vessel Phase	4
Prospects for Nuclear Microreactors: A Review of the Technology, Economics, and Regulatory Considerations	4
Optimizing the Implementation of Small Modular Reactors into Ontario’s Future Energy Mix	4
Evaluation of Decay Heat Calculation Uncertainties for Spent Fuel from RBMK-1500 Reactor	4
Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor	4
The UO ₂ Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program	4
Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju	4
Review of Detecting Anomalies in Power Reactors Using Neutron Noise Analysis	4
Validation and Neutronic Analysis of the CENM TRIGA MARK II SCALE Research Reactor Model: Computations Versus Experiment	4
Investigation of the Thermal Effects of MgO and ZnO Nanoparticles in a Pressurized Water Reactor Coolant with Computational Fluid Dynamics Model	4
Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel	4
CFD Modeling of Lead Solidification and Natural Convection in Support of the Westinghouse Lead-Cooled Fast Reactor Development	4
Diagnostic Technique Characterizing Neutron Irradiation Effects on Additively Manufactured Inconel 625 Eliminating the Need for Remote Handling	4
Rationally Designed Core-Shell Structured Fe ₃ O ₄ @NiFe-LDH Using MIL-100(Fe) as an Intermediate	4
Enhancing Site Evaluation Standards for Nuclear Power Plants in Indonesia: Human-Induced External Events	4
Correction	3
Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator	3
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods	3
Considerations for Hydride Moderator Readiness in Microreactors	3
Application of Systems Usability Case in an Integrated System Validation of Control Room	3
Magnetic Design and Analysis of a Scanning Magnet for Low-Energy E-beam Sterilization Applications	3
Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation	3
Advanced Reactor Control and Operations (ARCO): A University Research Facility for Developing Optimized Digital Control Rooms	3
Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools	3
Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima	3
Investigation of High-Temperature Compatibility of Select Oxides with Yttrium Hydride for Micro and Space Reactor Applications	3
High-Accuracy Pulse Shape Discrimination for LSO/LuYAP Crystals Using a CNN-BiLSTM Deep Learning Model	3
Experimental Performance Evaluation of Miniature Low-Area-Ratio Jet Pumps for High-Temperature Applications	3
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	3
In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis	3
Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE	3
Radiation Shielding for Electronic Cards Produced for Use on Cube Satellites	3
Techniques for Sensitivity Analysis in Severe Accidents: A Comparative Study	3
Study on Flow Characteristics of Integrated Natural Circulation Reactor Under Inclined Conditions	3
Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants	3
Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates	3
Preparation and Performance of a Self-Brittle Corrosive Bifunctional Detergent for Corrosive Deep Decontamination of Stainless Steel Surface Based on Controlled Polymerization by the RAFT One-Pot Meth	3
Commentary	3

The ENDF/B Nuclear Data Library and Its Impact on Reactor Simulations	3
Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides	3
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	3
Insights into the Economics of Decarbonizing Maritime Transport with Nuclear Fuel	3
Analysis of Influence of Tube Failure on Performance of Passive Residual Heat Removal Heat Exchanger	3
Numerical Investigation of Changes in Heat Transfer Coefficient of Water-Aluminum Oxide Nanofluid Cooling in Nuclear Reactors	3
Determination of the Gas Plenum Temperature of the P2M Instrumented Fuel Rodlets on the Basis of a Thermal-Hydraulic Study of the Belgian Reactor 2 Pressurized Water Capsule	3
Foreword: Special Issue Featuring Papers from the 2023 NEA Rising Stars Workshop	3
Development of Multiphase Mixture Model for Simulation of Sodium Aerosol Transport in Cover Gas Space of SFR Systems	3
Uncertainty and Sensitivity Analyses for Postulated Severe Accidents of Reference PWRs and SMRs in the Frame of the IAEA CRP and Relevant Insights	3
Silicon-Induced Microstructural Refinement in FeCrAl ODS Alloys for Accident-Tolerant Fuel Applications	3
SORT: Safety-Oriented Mobile Robot Teleoperation System for Nuclear Maintenance	3
Integrating Econometrics and Artificial Intelligence to Assess the Impact of Trade on Nuclear Proliferation	3
Foreword: Selected papers from the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)	3
Correlation Method of 3-D Detection of Distant Sources of Gamma Radiation and Neutrinos by Intensity Interferometry	3
A Study on Boiling Heat Transfer Performance of TiO ₂ -CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface	3
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1	3
Application of FSVD Algorithm to Airborne Gamma Detection of Trace Radionuclides in the Process of a High Radon Background	3
Technical Reviewers	3
Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding	3
Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications	3
Integral-Effect Test for Loss of Residual Heat Removal System During Mid-Loop Operation in ATLAS Facility	3
Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment	3
Discrete Active Disturbance Rejection Control Law Designed for Nuclear Reactor Under Load-Following Operation	3
Impact of Support Properties and Process Parameters on Performance of Supported Liquid Membrane for the Extraction of Uranium from Uranyl Nitrate Pure Solution and Its Mathematical Modeling	3
Parametric Analysis of Radiological Impact from Hypothetical Accident Scenario at the Sanmen Nuclear Power Plant	3
Preliminary Investigation of Gamma Radiation on the Chemical and Physical Characteristics of an Organic Coolant	3
Safety Assessment Methodology for Transportation of Radioactive Material via Train	3
Computational Framework for Estimating Cost of Equipment Disposal for Advanced Reactors	3
Preventing Reverse Engineering of Critical Industrial Data with DIOD	3
Thermal-Hydraulic Behavior and Safety Characteristics of the NHR200-II Reactor During Small-Break Loss-of-Coolant Accidents	3
A High-Temperature Gas-Cooled Reactor to Directly Reuse Spent Fuel: Analyzing the Effects on Core Performance Caused by Simple Core Modifications	3
Design and Demonstration of an Additively Manufactured Integrated Pressure Limiting Structure for Insertion into a Nuclear Research Reactor	3
Zombies, Superpowers, and Apocalyptic Narratives: Exploring Science Fiction as a Messy Space for Public Engagement on Radiation, Nuclear Power, and Solving Climate Change	2
Probabilistic Fracture Analysis for a Boiling Water Reactor Pressure Vessel During Transition to Decommissioning	2
Constitutive Modeling of Anisotropic Plasticity with ML Algorithms in Metals	2
Inferential-Statistical Reevaluation of Spent Fuel Zircaloy Cladding Integrity	2
Toward a Better Understanding of Reflood Thermal Hydraulics: A Summary of the OECD/NEA RBHT Project	2
Technoeconomic Design Optimization for Fast Reactors. Part I: Workflow Development and Case Study for Small LFR District Energy Application	2
A Pressure Drop and Particle Image Velocimetry Investigation into Depressurized Loss-of-Coolant Accident Parameters Applied to Packed Beds with an Aspect Ratio of D/d	2
Experimental Model to Study Characteristics of Radon Cover in Waste Landfills	2
Characterization of LuAG:Ce,Ca and LYSO:Ce,Ca Scintillators for Multiple Photon Emission	2
Benchmarking Neutron Counting System for Passive Measurements and Active Interrogation of Unknown Objects for Fissile and Fissionable Materials Determination	2
UaSA Application in Severe Accident Analysis: Challenges and Path Forward	2
Formation of Organic Tellurides and Organic Iodides Together Under Gamma Radiation	2
A Risk Approach to the Management for the Pre-Defueled Phase in the Decommissioning Transition Stage	2
Direct Numerical Simulation of Single- and Two-Phase Flows for Nuclear Engineering Geometries	2
Exploring the Feasibility of Kuiper Belt Missions Supported by Centrifugal Nuclear Thermal Propulsion	2
Foreword Special Issue on Advancements in Uncertainty and Sensitivity Analyses: Current Status and Perspectives	2
Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh	2
Bayesian Calibration of UO ₂ Creep Rates as a Tool for Accelerated Fuel Qualification	2
ENTS: A Novel Algorithm for Sampling-Based Dynamic Probabilistic Risk Assessment	2
Glove Operation Compartment with Cuboid Cans for Efficient Handling of Size-Reduced Solid Waste Generated from Plutonium-Contaminated Glovebox Dismantling Activities	2
High-Fidelity Modeling and Experiments to Inform Safety Analysis Codes for Heat Pipe Microreactors	2
Simplified Reactor Model for Microreactor Coupled with Helium Closed Brayton Cycle	2
Radioisotopes for Nuclear Medicine: An Overview	2
Thorium and Uranium, Specific Surfaces, and Minerals in Bentonites	2
Influence of Iodine Chemistry in I ₂ Scrubbing Modeling	2
Digitalization, Management, and Synthesis of Thermal-Hydraulic Legacy Data Using the Dynamical System Scaling	2
Localization of Stationary and Moving Radiation Sources Using a Feedforward Neural Network with an Array of Sensors	2
Automatic Generation of Event Trees and Fault Trees: A Model-Based Approach	2
Prediction of Flooding Characteristic in Pulsed Disc and Doughnut Extraction Column Using LASSO Method	2
A Fan-Controlled Sodium-to-Air Heat Exchanger Configuration for Failsafe Decay Heat Removal in Sodium-Cooled Fast Reactors	2
A Batch Refueling Framework for Implementing the Sourdough Fuel Cycle and Waste Management Strategy in the EIRENE Novel Molten Salt Reactor Design	2
Novel Approach for Network Data Exchange Among Safety-Related Control Systems of Nuclear Reactors	2
Prediction of Dispersed-Phase Holdup in Pulsed Disk and Doughnut Extraction Columns Using Machine Learning Methods	2
Technical Reviewers	2
High-Fidelity Velocity and Concentration Measurements of Turbulent Buoyant Jets	2
Comments on the Physics of the Frisch-Peierls Memorandum	2
Explainable, Deep Reinforcement Learning–Based Decision Making for Operations and Maintenance	2
Human Factors Considerations in Artificial Intelligence Applications for Nuclear Power Plants	2
Detecting Anomalies in Simulated Nuclear Data Using Autoencoders	2
Evaluation of Neutron Scattering and Shielding Behavior in Epoxy-hBN Composites for Nuclear Applications	2
Simulation and Mitigation of False Data Injection Cyberattacks on a Space Nuclear Reactor Power System	2
Scientific and Cultural Heritage in Argentina’s Nuclear Sector: Meanings and Dynamics of Activation at the Bariloche Atomic Center	2
Numerical Analysis of Heat Pipe Performance Considering Helium Gap Effects	2
Role of Accelerated Burnup Irradiation Testing in Support of Accelerated Fuel Qualification	2
Stability Tests and Analysis of a Low-Pressure Natural Circulation Loop with Flashing Instability	2
Analytical Model of Natural Circulation with a Sinusoidal Heat Input in a PWR	2
Evaluation of the New ENDF/B-VIII.0 Nuclear Data Library on Neutronic Parameters Calculations for First Core RSG-GAS Reactor	2
A MOOSE-Based Model for Fission Product Transport and Source Term Estimation for High-Temperature Gas-Cooled Reactors	2
Lumped Parameter Analysis of Autogenous Propellant Pressurization System for Nuclear Thermal Rocket	2
Preliminary Characterization of Alumina-Forming Austenitic–Type Advanced Alloys as Structural Materials for LFRs	2
Research Activities Associated with the Treatment of Potential Common-Cause Failures in Event and Condition Assessments	2
Exploring Public Discourse About Spent Nuclear Fuel Management on Twitter	2
Refueling Considerations for ⁹⁹ Mo Production in a CANDU Reactor	2
Numerical Simulations of Flow-Induced Deflections in MITR LEU Fuel Plate Due to Channel Size Disparity	2
Development of an Extended State Observer for Monitoring of a PWR Based on a Two-Point Kinetic Model	2
Startup and Multiphysics Analysis of a Compact kW-Class Thermal Spectrum Microreactor	2
Comparative Consequence Analysis for a Heat Pipe–Cooled, TRISO-Fueled Microreactor Operating Across Distinct Climates	2
Experimental and Numerical Reassessment of Real-World Defects in Nuclear Components Through Additively Manufactured Physical Twins	2
Assessment of Factory Fabrication Considerations for Nuclear Microreactors	2
Resilience Governance in Nuclear Safety: Insights from China’s AI-Driven Innovative Practices	2
Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR	2
Thermal Assessment of Repository Footprint Requirement for Advanced Fuel Cycles	2