Nuclear Technology

Article	Citations
Thermal-Hydraulic Core Design of a Thorium-Based Molten Salt Fast Energy Amplifier	60
Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications	35
Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark	21
Recent 238 Pu Production Activities at Idaho National Laboratory	21
FAST Irradiations, Postirradiation Examinations, and Modeling of U-Mo for Light Water Reactor Applications	20
An Anisotropic Neutron Collimating System for Proton Accelerator–Generated Secondary Particles	20
Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor	20
Nuclear Power Concepts and Development Strategies for High-Power Electric Propulsion Missions to Mars	17
STORAGE: A Source Term Model for Intermediate-Level Radioactive Waste	17
Comprehensive Study on p-n Junction and Schottky Barrier Betavoltaic Battery with 14 C Beta-Emitting Source	15
Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments	15
Spatiotemporal Evaluation of Bubble Characteristics in Sodium Using Real-Time X-Ray Imaging	15
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay	13
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor	13
Mapping the Hydrogen Economy in Ghana: The Strategic Contribution of Small Modular Reactors	12
Liquid Film Thickness for Gas-Liquid Annular Flow Across Grid Spacer with Vanes in Simple 3 × 3 Rod Bundle Channel	12
Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles	12
Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction	12
Enhancement of Fast Neutron Detection in Liquid Scintillator Detectors	11
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling	11
Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors	11
Comparison of Two Methods for Obtaining the Variabilities in a FRAM Model of a Combined Nuclear Facility Project	10
Development of a Signal Processing Software for Scintillation Detectors and Implementation on an FPGA for Fast Sensing	10
Boiling and Drying Accident of High-Level Liquid Waste in a Reprocessing Plant: Measurement of the Liquid-Phase Mass Transfer Coefficients of NO 2 and RuO	10
A Framework for Event Detection in Nuclear Facilities Using Wireless Sensors and Actors Networks	10

Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample	9
Network Graph Laplacian-Based Sensor Projection in System-Level Modeling of Liquid-Metal Loop	9
Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm	9
Revisiting Mobile Paste Reactor Fuel	9
Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle	9
Highly Available Nuclear Power in a Microgrid Configuration for the ORNL Distribution System	9
A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components	8
Thermal-Hydraulic Analysis of Inward and Outward Fuel Plate Buckling in a Typical MTR Reactor	8
Detection of Isotopes in Urban Source Search Low-Count Gamma Spectra Using Hopfield Neural Networks	8
A RELAP5-3D Model of the Lobo Lead Loop	8
Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks	8
Adsorption Properties of Cs(I) and Co(II) on GMZ Bentonite Colloids	8
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys	8
The Use of High-Density UN Fuel in Heat-Pipe Microreactors	8
Density Equation for Mixed Organic Solutions Containing tri- n -butyl Nitrate, n -Dodecane, Nitric Acid, and Nitrates of Heavy Metals	8
Organic Telluride Formation from Paint Solvents Under Gamma Irradiation	8
Comprehensive Study on Gamma-Ray, Neutron, and Charged Particle Shielding Properties of Glass Materials Using Analytical Methods and Monte Carlo Simulations	8
CHF Enhancement by γ-Fe 2 O 3 Nanofluids with Pool Boiling Condition on a Downward-Facing Plane	7
Validation Matrix for Pool Scrubbing Models	7
Study of the User Effect Impact in Forward Uncertainty Propagation Approaches Applied to Severe Accident	7
Assessing the Structure-Based Turbulence Model Performance for Thermal Striping Applications Using Symmetric Jet Experiments	7
Training Autonomous Robotic Tasks Through the Use of Machine Learning in Simulated Realities	7
Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application	7
Safety Benefits Assessment for Accident Tolerant Fuels in Consideration of Steam Generator Tube Degradation Using Dynamic Event Tree Analysis	7
Development of Two-Step Method for Fast Chloride MSR Neutronics	7
Development of Emergency Information System to Support Nuclear Power Plant Management in Severe Accident	6
Heat Transfer Analysis of Core Melt Contact with a CANDU Calandria	6
Development and Verification of Neutron Kinetics Parameter Calculation Program Applicable to Subcritical Systems of Long-Life Reactors	6
A Multiwire Proportional Chamber for Standardization of Large-Area Sources: Methodology and Challenges for In-House Construction	6
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors	6
Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor	6
Adaptive Model Predictive Control for Heat Pipe–Cooled Microreactors Under Normal and Heat Pipe Failure Conditions	6
Prognostics and Health Management for Maintenance-Dependent Processes	6
Effect of Nozzle Diameter on Quenching Behavior of Simulant Material CaO-Fe2O3 Under Bottom Flooding Conditions	6
Iodine Source Term Uncertainty and Sensitivity Analysis with the Severe Accident Code ASTEC: Focus on Iodine Chemistry, Aerosol Behavior, and Containment Pressurization	6
The Versatile Loop Facility: A New Infrastructure for Testing Components and Systems of Lead Fast Reactor Technology	6
Sparse-View Neutron Computed Tomography 3-D Reconstruction via the Fast Gradient Projection Algorithm	6
Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models	6
Optimizing the Implementation of Small Modular Reactors into Ontario’s Future Energy Mix	5
Indirect Parameterized Risk Assessment Applied to Brazilian Nuclear Sector	5
Assessment of Screen-Covered Grooved Sodium Heat Pipes for Microreactor Applications	5
Radionuclide Transport in Channel Networks with Radial Diffusion in the Porous Rock Matrix	5
Rationally Designed Core-Shell Structured Fe 3 O 4 @NiFe-LDH Using MIL-100(Fe) as an Intermediate Linker for Efficient Uranium Ads	5
Systematic Component Investigation of the Steady-State High-Temperature In-Pile Nuclear Thermal Propulsion Experimental Test Bed	5
Validation of a Hybrid Domain Overlapping Coupling Between SAM and CFD Against the TALL-3D Transients	5
Foreword: Special issue on the Nuclear Energy Advanced Modeling and Simulation Thermal Hydraulics Integrated Research Project	5
CFD Modeling of Lead Solidification and Natural Convection in Support of the Westinghouse Lead-Cooled Fast Reactor Development	5
Research on the Preliminary Prediction of Nuclear Core Design Based on Machine Learning	5
Prospects for Nuclear Microreactors: A Review of the Technology, Economics, and Regulatory Considerations	5
Validation of a Countercurrent Gas Flow Model for Use in the Kairos Power System Analysis Module (KP-SAM) Code	5

Multiphase Turbulence Modeling Using Sparse Regression and Gene Expression Programming	5
Build-to-Replace Strategy to Reduce Operations and Maintenance Costs for Advanced Reactors	5
2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE	5
Investigation of the Thermal Effects of MgO and ZnO Nanoparticles in a Pressurized Water Reactor Coolant with Computational Fluid Dynamics Model	5
Validation and Neutronic Analysis of the CENM TRIGA MARK II SCALE Research Reactor Model: Computations Versus Experiment	5
Diagnostic Technique Characterizing Neutron Irradiation Effects on Additively Manufactured Inconel 625 Eliminating the Need for Remote Handling	5
Direct Numerical Simulation and Large Eddy Simulation of a 67-Pebble-Bed Experiment	5
Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL	5
Finely Divided Metal as Nuclear Reactor Fuel	5
Acoustic Analysis of the Effects of Vapor-Liquid Interfacial Morphology on Pool-Boiling Heat Transfer	5
On the Development of a Novel Acoustic Flowmeter for High-Temperature Gas-Cooled Reactors	5
Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister Filling Process: Part 2	5
Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator	4
Application of FSVD Algorithm to Airborne Gamma Detection of Trace Radionuclides in the Process of a High Radon Background	4
Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor	4
Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima	4
On the Symmetry of Blast Waves	4
Modal Decomposition of the Flow in a Randomly Packed Pebble Bed with Direct Numerical Simulation	4
Neutron Energy Spectrum Measurement and Unfolding Method Based on a Single Long Lithium- or Boron-Doped Scintillator	4
Constructing Neural Network Model to Evaluate and Predict Human Error Probability in Nuclear Power Plants Based on Eye Response, Workload Rating, and Situation Awareness	4
The Experimental and Simulation Results of LIVE-J2 Test—Investigation on Heat Transfer in a Solid–Liquid Mixture Pool	4
The UO 2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program	4
Comparison of Neutron Radiation Response of Conventionally Wrought Versus Additive Manufacturing Production Methods in Alloy 625	4
Modeling of Lateral Flow in CFD for Subchannel Analysis	4
A Study on Boiling Heat Transfer Performance of TiO 2 -CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface	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
Evaluation of Decay Heat Calculation Uncertainties for Spent Fuel from RBMK-1500 Reactor	4
Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages	4
Equivalence of the Peierls and Serber Wartime Expressions for the Critical Radius of a Fissile Isotope	4
Enhancing Site Evaluation Standards for Nuclear Power Plants in Indonesia: Human-Induced External Events	4
Comment on Comparison Between Historic Nuclear Explosion Yield Formulas	4
Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation	4
Numerical Simulation on Dispersion of Hydrogen Leaked in Particle Layers of Glass Beads and Soil	4
Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications	4
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	4
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	4
Denoising Algorithm for Subtle Anomaly Detection	4
Nuclear Thermal-Hydraulic Phenomena: Bases and Challenges	4
Time-Dependent Experiment on Reactor Power Distribution Estimation by Ex-Core Detectors at UTR-KINKI	4
Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel	4
Remark About “Finely Divided Metal as Nuclear Reactor Fuel”	4
Path Toward a Breeding, Proliferation-Resistant, Thermal-Spectrum Molten Salt Reactor	4
Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding	3
Preventing Reverse Engineering of Critical Industrial Data with DIOD	3
Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo	3
Design and Demonstration of an Additively Manufactured Integrated Pressure Limiting Structure for Insertion into a Nuclear Research Reactor	3
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1	3
In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis	3
Analysis of Influence of Tube Failure on Performance of Passive Residual Heat Removal Heat Exchanger	3
Magnetic Design and Analysis of a Scanning Magnet for Low-Energy E-beam Sterilization Applications	3
Convolutional Neural Network–Aided Temperature Field Reconstruction: An Innovative Method for Advanced Reactor Monitoring	3
Numerical Investigation of Changes in Heat Transfer Coefficient of Water-Aluminum Oxide Nanofluid Cooling in Nuclear Reactors	3
Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates	3
The Trinity High-Explosive Implosion System: The Foundation for Precision Explosive Applications	3
Considerations for Hydride Moderator Readiness in Microreactors	3
Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides	3
A Redundancy-Guided Approach for the Hazard Analysis of Digital Instrumentation and Control Systems in Advanced Nuclear Power Plants	3
Development of a Potential Facility Risk Index for Nuclear Safety and Security Using a Terrorism Scenario with a Hypothetical Nuclear Facility	3
Foreword: Selected papers from the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)	3
Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants	3
Experimental Validation of Modeling and Simulation Capabilities of RELAP5-TMSR with the NNCL Experimental Facility	3
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	3
Study on Flow Characteristics of Integrated Natural Circulation Reactor Under Inclined Conditions	3
Correlation Method of 3-D Detection of Distant Sources of Gamma Radiation and Neutrinos by Intensity Interferometry	3
Commentary	3
Radiation Shielding for Electronic Cards Produced for Use on Cube Satellites	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
Impact of Steel Equipment on Cyclotron Activation and Its Implications for Radioactive Waste Management	3
Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools	3
Experimental Performance Evaluation of Miniature Low-Area-Ratio Jet Pumps for High-Temperature Applications	3
Clogging Properties of HEPA Filter Induced by Loading of Soot from Burned Glove-Box Panel Materials	3
Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment	3
Integral-Effect Test for Loss of Residual Heat Removal System During Mid-Loop Operation in ATLAS Facility	3
Investigation of High-Temperature Compatibility of Select Oxides with Yttrium Hydride for Micro and Space Reactor Applications	3
Safety Assessment Methodology for Transportation of Radioactive Material via Train	3
Integrating Econometrics and Artificial Intelligence to Assess the Impact of Trade on Nuclear Proliferation	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
Computational Framework for Estimating Cost of Equipment Disposal for Advanced Reactors	3
Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface	3
Multiphysics Analyses of the Bottom Components of the 3D Printed Transformational Challenge Reactor	3

Correction	3
Parametric Analysis of Radiological Impact from Hypothetical Accident Scenario at the Sanmen Nuclear Power Plant	3
Advanced Reactor Control and Operations (ARCO): A University Research Facility for Developing Optimized Digital Control Rooms	3
Canadian Contributions to the Manhattan Project and Early Nuclear Research	3
Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE	3
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods	3
Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju	3
Insights into the Economics of Decarbonizing Maritime Transport with Nuclear Fuel	3
Technical Reviewers	3
Application of Systems Usability Case in an Integrated System Validation of Control Room	3
Global Divergence in Nuclear Power Plant Construction: The Role of Political Decentralization	3
Improvement of Radiological Waste Characterization with Bayesian Machine Learning	2
Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly	2
Explainable, Deep Reinforcement Learning–Based Decision Making for Operations and Maintenance	2
Detecting Anomalies in Simulated Nuclear Data Using Autoencoders	2
Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh	2
Mixing of Hydrogen-Steam Buoyancy Jets Released into the Upper Atmosphere of the Containment Building	2
Exploring Public Discourse About Spent Nuclear Fuel Management on Twitter	2
Qualification of Metallic Fuel Data for Advanced SFR Applications	2
Automatic Generation of Event Trees and Fault Trees: A Model-Based Approach	2
Preliminary Results for In-Situ Alternative Propellants for Nuclear Thermal Propulsion	2
Safety-Related Instrumentation and Control Pilot Upgrade: Initial Scoping Phase Implementation and Lessons Learned	2
Investigation and Analysis of Thermoelectrically Cooled CZT Performance	2
A Risk Approach to the Management for the Pre-Defueled Phase in the Decommissioning Transition Stage	2
Experimental and Computational Verification of a New Remote Monitoring System Design for Spent Fuel Dry Cask Safeguards Using Small-Scale, Generic Diversion Scenarios	2
Resolution Analysis of Fast Neutron Imaging Based on D-T Neutron Source	2
Simplified Reactor Model for Microreactor Coupled with Helium Closed Brayton Cycle	2
Simulation and Mitigation of False Data Injection Cyberattacks on a Space Nuclear Reactor Power System	2
Prediction of Dispersed-Phase Holdup in Pulsed Disk and Doughnut Extraction Columns Using Machine Learning Methods	2
Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR	2
Bayesian Calibration of UO 2 Creep Rates as a Tool for Accelerated Fuel Qualification	2
Comments on the Physics of the Frisch-Peierls Memorandum	2
Electron Target Cooling Analyses of the KIPT ADS Using MCNP and Ansys Fluent	2
Refueling Considerations for 99 Mo Production in a CANDU Reactor	2
Direct Numerical Simulation of Single- and Two-Phase Flows for Nuclear Engineering Geometries	2
Release Behavior of Gaseous Ruthenium Tetroxide During Heating of High-Level Liquid Waste Simulant During Simulated Accident Conditions	2
Exploring the Feasibility of Kuiper Belt Missions Supported by Centrifugal Nuclear Thermal Propulsion	2
Thermal Assessment of Repository Footprint Requirement for Advanced Fuel Cycles	2
Probabilistic Fracture Analysis for a Boiling Water Reactor Pressure Vessel During Transition to Decommissioning	2
TRACE Assessment for Simulating Density Wave Oscillations in a Full-Scale BWR Rod Bundle Under Natural Circulation	2
Analytical Model of Natural Circulation with a Sinusoidal Heat Input in a PWR	2
Enhanced Video-Level Anomaly Feature Detection for Nuclear Power Plant Component Inspections Using the Latency Mechanism	2
i-LAMP: Global, Industrywide Learning Aging Management Program for Neutron-Absorber Materials in Spent Fuel Pools	2
Benchmarking Neutron Counting System for Passive Measurements and Active Interrogation of Unknown Objects for Fissile and Fissionable Materials Determination	2
Optimization of Elliptical U-Tube Heat Exchanger (EUTHE) for Spray Cooling Based on the Taguchi and CFD Method	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
Detailed Analysis of the Effects of Spacer Grid and Mixing Vanes on Turbulence in a PWR Subchannel Under DFFB Conditions Based on DNS Data	2
Toward a Better Understanding of Reflood Thermal Hydraulics: A Summary of the OECD/NEA RBHT Project	2
Experimental Model to Study Characteristics of Radon Cover in Waste Landfills	2
Design and Suitability Analysis of FPGA-Based TCP/IP Offload Module for Control Systems of FBRs	2
Numerical Simulations of Flow-Induced Deflections in MITR LEU Fuel Plate Due to Channel Size Disparity	2
Developing a Three-Dimensional Bubble Dynamics Model for Centrifugal Nuclear Thermal Propulsion	2
High-Fidelity Velocity and Concentration Measurements of Turbulent Buoyant Jets	2
Critical Assemblies: Dragon Burst Assembly and Solution Assemblies	2
Electrochemical Identification of Metal Chlorides in Eutectic LiCl-KCl Without Prior Knowledge of Analyte Identities	2
Numerical Analysis of Heat Pipe Performance Considering Helium Gap Effects	2
Design of Moderator Assemblies for Fast, Epithermal, or Thermal Neutron–Dominated n-γ Mixed Fields Using a D-D Neutron Source	2
Startup and Multiphysics Analysis of a Compact kW-Class Thermal Spectrum Microreactor	2
Influence of Iodine Chemistry in I 2 Scrubbing Modeling	2
Fiberoptic Laser-Induced Breakdown Spectroscopy System for in situ Measurement in a Hazardous Environment	2
Advanced Instrumentation and Modeling Framework for Two-Phase Flow	2
UaSA Application in Severe Accident Analysis: Challenges and Path Forward	2
Research Activities Associated with the Treatment of Potential Common-Cause Failures in Event and Condition Assessments	2
A Batch Refueling Framework for Implementing the Sourdough Fuel Cycle and Waste Management Strategy in the EIRENE Novel Molten Salt Reactor Design	2
Development of an Extended State Observer for Monitoring of a PWR Based on a Two-Point Kinetic Model	2
Uncertainty Quantification for Multiphase Computational Fluid Dynamics Closure Relations with a Physics-Informed Bayesian Approach	2
Optimized FSF Controller for Bulk Power Control of Large-Core PHWRs	2
Adapting the eVinci Microreactor into a Hybrid Power and Research Reactor Facility for Use at a University Campus	2
The Hypatia Experiment: Yttrium Hydride and Highly Enriched Uranium Critical Experiment	2
Trinity by the Numbers: The Computing Effort that Made Trinity Possible	2
Seismic Demand Sensitivity of Reactor Containment Building Using Bayesian Additive Regression Trees	2
SAM: A Modern System Code for Advanced Non-LWR Safety Analysis	2
Nuclear Science for the Manhattan Project and Comparison to Today’s ENDF Data	2
A Fan-Controlled Sodium-to-Air Heat Exchanger Configuration for Failsafe Decay Heat Removal in Sodium-Cooled Fast Reactors	2
Stability Tests and Analysis of a Low-Pressure Natural Circulation Loop with Flashing Instability	2
Thorium and Uranium, Specific Surfaces, and Minerals in Bentonites	2
Design and Application of an Airborne Radioactivity Survey System Based on Unmanned Aerial Vehicle	2
Adaptive Sampling Limit Surface Search Application to Identify Cliff-Edge Effects in Severe Accident Uncertainty Analysis	2
Alloying of U-Al-SS as a Simulant for Pu-Al-SS Alloying	2
Digitalization, Management, and Synthesis of Thermal-Hydraulic Legacy Data Using the Dynamical System Scaling	2
Performance Evaluation of Batchwise Multistage Countercurrent Extraction in a LiCl–KCl/Cd System to Separate Actinides from Rare Earth Fission Products	2
Bayesian Network–Based Fault Diagnostic System for Nuclear Power Plant Assets	2
Inferential-Statistical Reevaluation of Spent Fuel Zircaloy Cladding Integrity	2
High-Fidelity Modeling and Experiments to Inform Safety Analysis Codes for Heat Pipe Microreactors	2
Hydride Transformations and Their Impact on Zirconium Alloy Cladding Embrittlement During Spent Nuclear Fuel Storage	2
Novel Approach for Network Data Exchange Among Safety-Related Control Systems of Nuclear Reactors	2
Human Factors Considerations in Artificial Intelligence Applications for Nuclear Power Plants	2
The Taming of Plutonium: Plutonium Metallurgy and the Manhattan Project	2
Lumped Parameter Analysis of Autogenous Propellant Pressurization System for Nuclear Thermal Rocket	2
Constitutive Modeling of Anisotropic Plasticity with ML Algorithms in Metals	2
Role of Accelerated Burnup Irradiation Testing in Support of Accelerated Fuel Qualification	2
Assessment of Factory Fabrication Considerations for Nuclear Microreactors	2
Pressurized Thermal Shock Analysis with Uncertainty Propagation for the APAL Project Using TRACE and FAVOR	1
Evaluating Methods of Software Bill of Materials Generation to Enhance Nuclear Power Plant Cybersecurity	1
Multi-Criteria Optimization of a Nuclear Marine Propulsion System: A Thermoeconomic Approach	1